Text

Forwards Emergency Procedure Guideline Deviation Justification Forms Per SER Section 13.5.2.3 Confirmatory Item 60.Evaluation Underway to Ensure That Emergency Operating Procedures Consistent W/Fsar Design Basis
	ML20101U267
Person / Time
Site:	River Bend
Issue date:	01/15/1985
From:	Booker J; GULF STATES UTILITIES CO.
To:	Harold Denton; Office of Nuclear Reactor Regulation
References
	RBG-19-891, NUDOCS 8502070217
	Download: ML20101U267 (150)
	v • d • e

GULF STATES UTILITIES COMPANY M*w

, , o w

January 15, 1985 RBG- 19,891 File Code: G9.5, G9.33.4 ,

2 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Denton:

River Bend Station - Unit 1 Docket No. 50-458 Gulf States Utilities Ccmpany (GSU) submits the attached Emergency Procedure Guideline (EPG) deviation justification forms as requested in g the Nuclear Regulatory Commission's (NRC) Safety Evaluation Report (SER)

Section 13.5.2.3, Confirmatory Item No. (60). To assist your review, the following information is attached:

Attachment 1 - River Bend Station (RBS) EPG Deviation Justification Forms on Technical Matters.

Attachment 2 - RBS Emergency Operating Procedures (EOP), Rev. 1.

The Author's Guide / Control and Use Procedures, OSP-0009.

incorporated accepted human engineering principles. Therefore, editorial differences may exist between the BWR Owner's Group (BWROG)

EPG's, RBS E0Pa and applicable AOPs. GSU's review of E0Ps and comparison with the BWROG EPGs, Rev. 3, identified no safety significant deviations. However, deviations from the EPGs judged to be of technical substance are documented and justified on the attached deviation justification forms.

i During the initial E0P verification and validation phase, it was g determined that some E0P steps were event oriented. To provide cohesive j gl a

guidance to the operator and utilize good human engineering principles, N event oriented E0Ps were combined into existing plant AOPs. Technical deviations from the EPGs incorporated into plant AOPs are documented on attached deviation justification forms.

As stated in GSU's February 27, 1984 letter to your office, an -

engineering evaluation is being performed to ensure EPC/EOP assumptions are consiste'.t with the design basis described in the RBS Final Safety Analysis Report.

hC 8502070217 850115 ,

PDR ADOCK 05000458 PDR 1 g

E k

s i

t e

Mr.'Denton January 15, 1985 Future changes to the E0Ps'will be evaluated in accordance with Operating Station Procedures (OSPs).

Sincerely,

/J.E. Booker Manager-Engineering

' Nuclear Fuels & Licensing

- River Bend Nuclear Group JEB/RJK/je

' Attachments.

s

'5 s

y t

~

s.-.

L2- .- __. i -'}

5

Attachment 1 6

RBS EPG Deviation Justification Forms on Technical Matters

__ l

1 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: Cautions #1 - #8 E0P STEP: None JUSTIFICATION OF DIFFERENCES:

General cautions are implemented in the training program and not

-included in the E0P's in accordance with OSP-0009. Step 4.7.1.1.

DATE: 1/14/85 E0P WRITER:

//

u f

2 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT

- EPG STEP: Caution fil 4'

EOP STEP: E0P-0001, Caution i1 JUSTIFICATION OF DIFFERENCES:

Deleted.last sentence of Caution fil. Operators are trained to restore LPCS and LTCI to standby as soon as possible.

DATE: 1/14/85' EOP WRITER: k N s p I

3 !

SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: RC/Q; RC/L; RC/P EOP STEP: 1. Added E0P-0001, Steps 3.1.3, C3.1.3, and Note 1.

2. Deleted steps concerning an ATWS condition from the above EPG's and established a seperate ATWS procedure incorporating these steps.

JUSTIFICATION OF DIFFERENCES:

E0P-0001'was reorganized deleting all ATWS related steps from the E0P and establishing a separate ATWS procedure (A0P-0021). This reorganization was performed to simplify the E0P's for non-ATkS events.

The ATWS event requires the operator to perform steps that are contrary to the actions. required for non-ATWS events. It also provides more cohesive l guidance for the operator in an ATWS event. The necessity for this reorganization was indicated during the operator training and during the control room design review and E0P V&V. Steps 3.1.3, C3.1.3, and Note I were added to provide guidance on when to enter the ATWS or

' normal scram' procedure.

DATE: 1/14/85 E0P WRITER: O W h

5

4 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: First box of RC/P; First " bullet" E0P STEP: E0P-0001, Step 3.3.2.1 and C3.3.2 added additional requirement JUSTIFICATION OF DIFFERENCES:

Added requirement "and boron injection is not required'. If boron injection is required, the operator should not simply depressurize since it would introduce positive reactivity (from cooldown).

Procedure directs him to complete A0P-0021 " anticipated transient without scram".

DATE: 12/6/84 E0P WRITER: 'd G

5 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT

~ EPG STEP: RC/P-3 E0P STEP: E0P-0001, Step 3.3.5 JUSTIFICATION OF DIFFERENCES:

L- 1. Added requirement to have water level stabilized since this is the intent specified in Appendix B

2. Added entire SLC tank since (lbs) is not in the panel indicator.

DATE: 12/6/84 E0P WRITER: k )VW b

I r

6

' SUPPORTING DOCUMENTATION OF E0P DEVELOPMEh"I

' EPG STEP: Contingency 2

- EOP STEP: 'EOP-001, Step 3.3.6 J +

w JUSTIFICATION OF DIFFERENCES:

. 1. Deleted IC; this is not included'in RBS design.

2. Added "if available, open all turbine bypass valves". This is preferable to ADS due to energy release to Suppression Pool. This is technically consistent with EPG's; it simply puts it "up front" in the Emergency Depressurization step in case it was missed in 3.3.2.

4 The remaining E0P's direct the operator to this step whenever Emergency RPV Depressurization is required.

3. Contingency 2 was integrated into the RPV pressure control section of EOP-0001 based on observations in V&V. This reduces branching.-

DATE: 12/6/84 E0P WRITER: L hj

()

i

~

7 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: Contingency #2, Step C2-1.3 E0P STEP: E0P-0001, Step C3.3.6.3 JUSTIFICATION OF. DIFFERENCES:

t

. The E0P does not provide the EPG direction for operator actions given less than 7 SRV's, but not less than 3 SRV's can be opened. This E0P step will be revised to include the intent of the EPG step.

DATE: 1/14/85 E0P WRITER:- M G

- - ,% , . - - . - . , . . . - m. -. - - r-

8 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: C2-1.3 E0P STEP: E0P-0001, Step C3.3.6.3 Deleted Reference to Minimum SRV Re-opening Pressure ,.

JUSTIFICATION OF DIFFERENCES:

- The S/RV design at RBS can re-open at 'O' PSIG.

- DATE: 1/14/85 E0P WRITER: ~

k

()

av i L

9 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: -RC/P-4 E0P STEP: Added E0P-0001, Caution #18 JUSTIFICATION OF DIFFERENCES:

-To provide an additional caution to operators to maintain RPV level below +55" if boron has been inserted to prevent boron dilution.

.DATE: 1/14/85 E0P WRITER: O, O

m

~

10 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: Contingency 7 in its entirety RC/Q-2 through RC/Q5.6 EOP STEP: Not in E0P's. All of these steps are included in A0P-0021 " Anticipated Transient Without Scram" JUSTIFICATION OF DIFFERFNCES:

1. This is an event readily identifiable by the operators. The A0P's are event based Abnormal Operating Procedures.

2. E0P V&V program supports a separate procedure for ATWS. Integration into the E0P's proved cumbersome for the operators to implement.

3. Current training' experience indicate less problem dealing with ATWS events with the current configuration.

4. GE will review AOP-0021 to assure its steps incorporate contingency 7 and RC/Q-2 through RC/Q5.6.

DATE: 12/6/84 E0P WRITER: 8h 1

0 m

11 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: RC/Q-3, RC/Q-4 E0P STEP: A0P-0021, Steps 4.2 & 4.3 JUSTIFICATION OF DIFFERENCES:

1. Reversed the order of steps to assure SLC is considered for initiation earilier in the transient.

2. Most of the recirculation flow reduction will occur when the pumps

'are transferred to Low Frequency Motor Generator. This change was made based on observations during V&V.

-3..The procedure requires that the operator determine by all available means that power is above 5% before tripping recirculation pumps.

4. Operator training will insure that indeterminate power levels are assumed to be above 5%.

DATE: 1/14/85 E0P WRITER: ~

N

()

e

12 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: RC/Q-5 E0P STEP: AOP-0021, Step 5.2 JUSTIFICATION OF DIFFERENCES:

'I. Details of inserting control rods are put into A0P-0021 Enclosure 1

.to avoid clutter.

2. This is an option recommended by the BWR Owners Group and was found to be necessary during E0P V&V.

'DATE: 12/6/84 E0P WRITER:

U

l 13 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: RC/Q-5.4 EOP STEP: Added AOP-0021, Steps C5.2.1.4 JUSTIFICATION OF DIFFERENCES:

Since the CRD_HCU's hydraulic system, and test switches are located inside containment,.they may not be accessible during ATWS conditions.

Additional information is therefore provided if containment is inaccessible.

DATE: 1/14/85 E0P WRITER: dt b

L l

I'

- , _ _ . , _ . _ _ , , .._.- . - - . y- , ,~, . - --

16 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: Caution f20 E0P STEP: AOP-0021, Step C5.2.1 JUSTIFICATION OF DIFFERENCES:

1. No "hard-wired"' bypass is provided in the RBS RCIS. Other possible

~ bypass techniques will be evaluated and included in the revision to A0P-0021 as appropriate.

DATE: 1/14/85 E0P WRITER: O t

15 i

SUPPORTING DOCUMENTATION OF EOP DEVELOPMENT t,

EPG STEP: C7-2' E0P. STEP: AOP-0021, Step 5.6 JUSTIFICATION OF DIFPERENCES:

1.- Technical intent is to maintain reactor water level above top of

. active fuel. It is inadvisable to cause level fluctuation at this point due to other RPV stabilization concerns.

2.--Water level is restored to normal in Step 5.7.

3. This change was made based on observation during V&V.

DATE: 1/14/85 EOP WRITER: M 4 34.

()

16

' SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT

.EPG STEP: C7-2.1

-E0P STEP: AOP-0021, Step 5.6.3 JUSTIFICATION OF DIFFERENCES:

This EPG step was omitted from A05-0021. The intent of this EPG will be

-added to AOP-0021.

DATE: 1/14/85' EOP WRITER: . Oi A 6

i

17 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: C7-3 E0P STEP: AOP-0021, Step 5.9 JUSTIFICATION OF DIFFERENCES:

1. Cold shutdown baron weight was used as a conservative value because

-plant conditions may require cooldown in order to restore and maintain RPV water level.

2.~.EPG Step C7-3 requires restoration of water level to normal range if all rods are inserted past minimum suberitical withdrawal position.

This step was ommitted from AOP-0021 and the intent will be added to this procedure.

DATE: 1/14/85 E0P WRITER: di O

g m:3m--- ,-,,. ,w- , , -

18 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: C-7 Box Prior to C7-4 E0P STEP: AOP-0021 4 - JUSTIFICATION OF DIFFERENCES:

Omitted box prior to EPG Step C7-4. The intent of this step is

. incorporated into River Bend Station Operating Procedures.

DATE: 1/14/85 E0P WRITER: Mk O

o I

i a4 s

M l '.

19 l l

)

SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: Caution 26; C7-1 EOP' STEP: A0P-0021, Step 5.4 Cauwtion #2.

JUSTIFICATION OF DIFFERENCES:

Caution #2 reflects' Caution #25 of EPG, not Caution #26. Intent of Caution #26 will be incorporated in A0P-0021.

DATE: 1/14/85~ E0P WRITER: Q y.

L i.1 l

ti };

20 SUPPORTING DOCUMENTATI0" 0F E0P DEVELOPMENT EPG STEP: Box Before C7-1 EOP STEP: A0P-0021, Step 5.1

' JUSTIFICATION OF DIFFERENCES:

The EPG step was omitted and will be added to AOP-0021.

DATE .1/14/85 EOP WRITER:

M4b b

p

21 SUPPORTING DOCUMENTATION OF E0P DEVE10PMENT EPG STEP: Radioactivity Release Control Guideline in its entirety EOP STEP: Not in'EOP's - All of these steps are included in AOP-0022 " Radioactivity ease' JUSTIFICATION OF DIFFERENCES:

1. This is an event readily identifiable by the operators. The AOP's are event base Abnormal Operating Procedures.

2. EOP.V&V program supports a separate procedure for Radioactivity Release. Integration into the E0P's proved cumbersome for the operator to implement.

3. Current simulator class is having less problem dealing with Radioactivity Release events with the current configuration.

4. Radioactive Release is also covered in EIP's.

5. CE will review AOP-0021 to assure its steps incorporate the

-': Radioactivity Release Control Guidelines.

6. Added immediate operator action to conform with Abnormal Operating Procedure Format.

DATE: 1/14/85 E0P WRITER: d ,,

h

-l

22 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: Primary Containment Control Guideline Entry Condition on DW Pressure E0P STEP: E0P-0002, Step 2.4 Added "or Containment to Annulus Differential" JUSTIFICATION OF DIFFERENCES:

The MARK-III design at RBS requires monitoring of the containment to annulus differential pressure to maintaint containment integrity.

DATE: Jp4/85 E0P WRITER: N4 -

8 I

23 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: SP/T-3

-'EOP STEP: E0P-0002, Step 3.1.3 JUSTIFICATION OF DIFFERENCES:

1. Specified IF rather than BEFORE to give the operator more specific guidance and to preclude premature scrams.

2. Since the scram can be effected within~less than 10 seconds, it is not necessary to have an anticipatory time delay built in.

DATE: 12/6/84 E0P WRITER: dkV O

d L_ _ _ _ .

24

'f SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: DW/T EOP STEP: E0P-0002, Step 3.2 Added Caution f5 JUSTIFICATION OF DIFFERENCES:

The RBS design allows the hydrogen mixing system to aid in controlling DW temperature, so a caution was added to provide guidance to closely

- monitor containment pressure and temperature while using this syster.

DATE: 1/14/85 E0P WRITER: O~

b 5A,

l l

25 4

SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: DW/T-1 E0P STEP:~ E0P-0002, Step 3.2.1 JUSTIFICATION OF DIFFERENCES:

1. Specified IF instead of WHEN; see OSP-0009, Step 4.7.1.3.

2. Provided interim actions such as drywell purge, Hydrogen mixing, and controlled RPV depressurization before Emergency RPV depressurization.

' 3. The River Bend Station design does not include drywell sprays.

4. These interim steps were shown to be effective in mitigating High Drywell Temperatures during performance of the V&V.

DATE: 12/6/84 E0P WRITER:

dO 6

26 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: DW/T-3

.EOP STEP: E0P-0002, Step C3.2.1 JUSTIFICATION OF DIFFERENCES:

Added an intermediate step to begin a controlled cooldown at 180 F rather than wait until 340 F to begin rapid depressurization.

DATE: 1/14/85 E0P WRITER: bd'W e 6

.E

1 l

27 i

l SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT l

EPG STEP: DW/T-2 E0P STEP: E0P-0002, Caution 6 Added JUSTIFICATION OF DIFFERENCES:

Caution #6 was added based upon earlier RBS design. The RBS design has been changed and Caution'f6 will be delet:J.

DATE: 1/14/85 -E0P WRITER: O

(<

28 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: DW/T-2 E0P STEP: E0P-0002, Step 3.2.2.2 JUSTIFICATION OF DIFFERENCES:

1. Added assuring reactor is scrammed and open two SRV's since these are the first actions required to flood the reactor. Flooding is entered through E0P-0001 as specified in EPG's.

2. These steps more directly and more explicitly direct the operator to flood the RPV and reduces branching.

3. Changes were made as a result of observations during V&V.

DATE: 12/6/84 E0P WRITER: M Q , V' -C' U

\

& ,n . , , , . . . . . . - - - . . . . . , , - - . ~ - -. , . , .

29 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: CN/T-1

. EOP STEP: E0P-0002, Step 3.3.1 JUSTIFICATION OF DIFFERENCES:

1. Specified IF rather than WHEN; see OSP-0009, Step 4.7.1.3.

2. Last sentence added as a clarification based on observation during V&V.

DATE: 12/6/84 E0P WRITER: M 4 4/

O J

V

30 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: CN/T-2 E0P STEP: E0P-0002, Step 3.3.3 - Added JUSTIFICATION OF DIFFERENCES:

1. -Added as an interim measure to reduce containment temperature before RPV depressurization.

2. Containment purge can be an effective mechanism for reducing containment temperature.

DATE: 12/6/84 E0P WRITER: '

k.

()

e

31 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: PC/P-1 E0P STEP: E0P-0002, Steps 3.4.1, 3.4.3 JUSTIFICATION OF DIFFERENCES:

Containment ventilation system operates to maintain design conditions and to remove heat generated within the containment. In addition, Step 3.4.1 allows use of containment purge if no primary boundary leakage exists.

DATE: 1/14/85 E0P WRITER: M4 6

32 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: None E0P STEP: I EOP-0002, Step 3.4.2 JUSTIFICATION OF DIFFERENCES:

.The operator is directed to depressurize at 200 F/hr or emergency depressurize when the containment to annulus differential pressure

-reaches 5 paid. The additional operator action is required by FSAR analysis, Section 6.2.1.1.3.4.

DATE: 1/14/85 E0P WRITER: C A 0

1

33 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: PC/P-6

'EOP STEP: E0P-0002, Step 3.4.4/C3.4.4 JUSTIFICATION OF DIFFERENCES:

1. The suppression pool is a likely source of thermal energy in the containment and initiating suppression pool cooling can be effective in reducing containment pressure.

2. Suppresion pool cooling is operated in conjunction with the ventilation system to maintain containment temperature below 185 F and pressure =.< 2 Psig.

3.-There are no suppression pool sprays in RBS design.

4.;There are no drywell. sprays in RBS design.

DATE: 1/14/85 E0P WRITER: Q -

b

34 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: SP/L-3, Note.

E0P STEP: E0P-0002, Step 3.5.3 & 3.5.4 JUSTIFICATION OF DIFFERENCES:

Due to the plant specific configuration of the suppression pool load limit curve, Step 3.5.3 and 3.5.4 will be performed consecutively rather than concurrently.

DATE: 1/14/85 EOP WRITER: 4 2 - : r=

()

35 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: SP/L-3.2 E0P STEP: E0P-0002, Step 3.5.4 JUSTIFICATION OF DIFFERENCES:

SLC and CRD are located inside containment in the River Bend Station Design and were not considered as external to the containment. The intent of the EPG step is to consider sources of water external to the suppression pool. The intent of EPG setp SP/L-3.2 will be incorporated in the E0P.

DATE: 1/14/85 E0P WRITER: Q a-0

36 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: Contingency #1 EOP STEP: E0P-0004 JUSTIFICATION OF DIFFERENCES:

The Contingency #1 was rewritten as a seperate E0P to conform with the format of the RBS operating procedures.

DATE: 1/14/85 E0P WRITER: Md i M

37 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: Cl-7 E0P STEP: E0P-0004, Step 3.2.9 JUSTIFICATION OF DIFFERENCES:

1. CRD is started since it is a source of high pressure, high quality water.

2. Steam cooling steps (3.2.9.1) are incorporated into E0P-0004. This is to provide better integration and less branching. This was recommended by GE in their initial rcview and was indicated as a necessary move during the V&V process.

DATE: 12-6-84 E0P WRITER: d 1 -

0 e

L

38 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: Cl-7 E0P STEP: E0P-0004, Step C3.2.9 JUSTIFICATION OF DIFFERENCES:

Changed the requirement from one injection subsystem to two injection subsystems - during the V&V, the operators considered the CRD system to be an injection subsystem although it could be inadequte when used alone. The step will be rewritten requiring one injection subsystem regardless of CRD availability.

DATE: 1/14/85 E0P WRITER: _ d f,t 0

39 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: Cl-8 E0P STEP: E0P-0004, Step 3.2.10 JUSTIFICATION OF DIFFERENCES:

The statement "if no HPCS or LPCS subsystem is operating" was deleted.

Appendix B of the EPG's allowed using alternate injection subsystems prior to using core spray systema as currently written in the E0P. The decision has now been made to use the core spray systema prior to use of the alternate injection subsystems and the E0P will be revised.

DATE: 1/14/85 E0P WRITER: O #

O

40 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: Cl-8 E0P STEP: E0P-0004, Step 3.2.10 JUSTIFICATION OF DIFFERENCES:

Included contingency #4 steps in here to provide better integration and less branching and was recommended by GE in their initial review. The need for this integration was also observed during V&V.

DATE: 12/6/84 E0P WRITER: Nd4 0

41 SUPPORTING DOCUMENTATION OF EOP DEVELOPMENT EPG STEP: Contingency #3 in its entirety E0P STEP: E0P-0001, Step 3.3.3.2 E0P-0004, Step 3.2.9.1

-. JUSTIFICATION OF DIFFERENCES:

1. Included in E0P-0001 instead of a separate procedure to provide more

' direct integration and reduce branching.

2. This integration was recommended by GE during their initial review of the Draft E0P's.

3. EOP V&V supports integrating these steps into E0P-0001 and E0P-0004 so that RPV level control and/or level restoration steps are together and reduce branching.

4. Current training experience indicates less problems dealing with RPV pressure control with the current configuation.

5. GE will review EOP-0001 and E0P-0004 to assure contingency #3 is incorporated as stated.

6. RBS design does not include Isolation Condensors.

DATE: 1/14/85 EOP WRITER: 4. 3V k

1

l 42 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: Contingency #4 E0P STEP: E0P-0004, Step 3.2.10 JUSTIFICATION OF DIFFERENCES:

1. Included in E0P-0004 instead of a separate procedure to provide more direct integration and reduce branching.

2. This integration was recommended by GE during their initial review of the Draft E0P's.

'3. E0P V&V supports integrating these steps into E0P-0004 so that level restoration steps are in one procedure and reduce branching.

4. Current training experience indicates less problems dealing with RPV pressure control with the current configuration.

5. CE will review E0P-0004 to assure contingency #4 is incorporated as stated.

.DATE: '1/14/85 E0P WRITER: 1Qk D

43 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: Contingency #6 E0P STEP: E0P-0005 - General; organized into 3 modes of flooding

- these do not include flooding with boron and no level indication.

JUSTIFICATION OF DIFFERENCES:

1.'V&V uncovered major problems with implementing the EOP's when organized per the EPG's.

2. Flooding with boron and no level indication is virtually an impossible task and having these steps in the E0P cluttered the

. procedure. .This scenerio is covered, however; the operator will

" hold" the level as required to maintain MARFP and will not flood up until level indication is restored.

DATE: 12-6-84 E0P WRITER: Q[ _

0

44 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT l

EPG STEP: Box after C6-2.1 E0P STEP: E0P-0005, Steps 3.1 & 3.3 JUSTIFICATION OF DIFFERENCES:

-1. Level indication is assumed to be available during these flooding Bodes.

2. This does not result in a technical problem since the operator will hold at MARFP until level is restored or until control rods are inserted.

DATE: 12-6-84 E0P WRITER: k et ~

6

45 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: C6-2.2 EOP STEP: E0P-0005, Step 3.1.3 JUSTIFICATION OF DIFFERENCES:

1. Requirement to determine RPV pressure is below MARFP before cosmencing injection. Wording in EPG was confusing to the operator as observed during V&V.

2. No technical impact since this requirement is imposed in C6-2.1.

3. Added requirement to open additional SRV's if only low pressure systems are operable since MARFP is above shutoff head with 2 SRV's open. The EPG's say '....at least...SRV's".

DATE: 12-6-84 E0P WRITER: 1/ ~

f z

46 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: C6-3 E0P STEP: E0P-0005, Step 3.2 JUSTIFICATION OF DIFFERENCES:

1. Addressed as a separate mode to reduce the operator " decision blocks" down to a reasonable level, identified in the V&V program.

2. Added ' qualifier' on low pressure systems so the operator will have direction to open more SRV's. This is technically justifiable since the EPG's say "...at least SRV's".

DATE: 12-6-84 E0P WRITER: 4[

f

47 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: C6-6 E0P STEP: E0P-0005, Step 3.3.4 JUSTIFICATION OF DIFFERENCES:

1. This step is not in section 3.1 and 3.2 since flooding under these circumstances is for other considerations that must be met before the containment. pressure can be restored (i.e., you can't go back to E0P-0001 until: (a) all rods are at (04) and (b) RPV level indication is operable).

DATE: 12/6/84 E0P WRITER: 6f4/

0 u

48 1

SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: Contingency #5 in its entirety E0P STEP: ?Iot ir. E0P's. All of these steps are included in A0P-0020 " Alternate Shutdown Cooling" JUSTIFICATION OF DIFFERENCES:

1. This is an event readily identifiable by the operators. The AOP's are event based abnormal operating procedures.

2. The BWR OG Emergency Procedures Committee is considering deleting contingency #5 from Revision 4 of the EPG's.

3. E0P V&V program supports a separate procedure for Alternate Shutdown Cooling. Integration into the E0P's proved cumbersome for the operator to implement.

4. Current training experience indicates less problem dealing with Alternate Shutdown Cooling events with the current configuration.

S. GE will review AOP-0020 to assure its steps incorporate contingency f5 in its entirety.

DATE: 1/14/85 E0P WRITER: d 9

+

49 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: None in Contingency #5 E0P STEP: A0P-0020, Step 5.1 JUSTIFICATION OF DIFFERENCES:

1. This is a condition for Alternate Shutdown Cooling but is not specified in Contingency #5. It is possible that the operator could be using this AOP and not meet the entry conditions in E0P's. Since this condition is specified/ implemented in the EPG for RPV control it is needed to be specified here.

2. This does not alter the technical content of AOP-0020 as it relates to contingency #5.

DATE: 12-6-84 EOP WRITER:

d f#

g/

u.-

50 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: C6-1 was deleted EOP STEP: E0P-0005, Step 3.1, 3.2.4 JUSTIFICATION OF DIFFERENCES:

During conditions that require boron injection and the HSIV & main steam line drains are open or RCIC is operating, it would not be prudent to isolate these heat sinks and divert the heat to the containment.

DATE: 1/14/85 E0P WRITER: 4k 8

51 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: . C6-2.2 EOP STEP: E0P-0005, Step 3.1.3 JUSTIFICATION OF DIFFERENCES:

Added steps to ensure that the RPV pressure is above MARFP, but as low as possible to reduce the heat load as much as possible.

DATE: 1/14/85 E0P WRITER: Q [4 6

h I

, e

'l

52 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: C6-2.2 E0P STEP: E0P-0005, Step C3.1.3 JUSTIFICATION OF DIFFERENCES:

A statement in the EPG's concerning increasing flow with the

, non-preferred systems until "the RPV pressure is above MARFP" was omitted. This statement will be added to the EOPS.

DATE: 1/14/85 EOP WRITER: O v-

~

3

=-

53 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: None in contingency #5 E0P STEP: A0P-0020, Step 5.3

.- JUSTIFICATION OF DIFFERENCES:

Must evacuate containment before opening SRV's for personnel protection.

DATE: 1/14/85 E0P WRITER: Oh 0

r i

L_

56 SUPFORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: C6-5.1, C6-5.2 E0P STEP: None JUSTIFICATION OF DIFFERFNCES:

- Due to the RBS design , the water level instrumentation fill connections are located inside containment. During postulated events that would cause loss of the reference line water level, the containment is uninhabitable. The EPG step was based on the Mark I design where the fill lines may be accessible.

DATE: 1/14/85 E0P WRITER: d f 0

l s-

55 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: C5-3 E0P STEP: A0P-0020, Step 5.5 JUSTIFICATION OF DIFFERENCES:

1. Provide explicit instructions to the operator to assure 2 and only 2 SRV's are open.

2. This clarification was identified as being needed during V&V.

3. Does not alter the technical content of the corresponding EPG step.

DATE: 12-6-84 E0P WRITER: d .

O G _ - . . - -

56

- SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: None in contingency f5 EOP STEP: AOP-0020, Caution before 5.6 JUSTIFICATION OF DIFFERENCES:

Recent GE analysis indicates there may be some conditions /RPV pressures that may cause concern to monitor SRV discharge lines. The pressure is left as (later) until further analysis is received from CE.

DATE: 1/14/85 E0P WRITER: Q_ 1 h

57 SUPPORTING DOCUMENTATION OF E0P DE7ELOPMENT i

EPG STEP: C5-5 E0P STEP: A0P-0020, Step 5.7 JUSTIFICATION OF DIFFERENCES:

1. Specified preference for shutdown cooling inlet (VSLPCI) due to

. potential damage to LPRM strings if LPCI inject point is used.

- 2..This change is consistent with the technical intent of the EPG step.

f 1

DATE: 1/14/85 E0P WRITER:

NQ - -- __

V g.- me-yy>g ?aw,., ,-,,,y,-p,,

58 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: C5-6 ,

E0P STEP: AOP-0020, Step 5.8.1 t

4 JUSTIFICATION OF DIFFERENCES:

1. Specified methods the operator can use to determine RPV cooldow2 rate.

2. This addition is consistent with the technical content of the EPG step.

DATE: 1/14/85 E0P WRITER: k 0

ll-e'-

a op ~m-g--,gw y.9m- -=9Casq.t g p =4mb -

e,---r=-'--%,m.--- p 7 --Ma.-- p p ywy---

% e

59 l

l l

SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: C5-6.3 E0P STEP: A0P-0020, Step 5.11 4

JUSTIFICATION OF DIFFERENCES:

Deleted discussion of minimum S/RV opening pressure since the RBS design

-allows opening of S/RV's at 0 PSIG.

DATE: 1/14/85 E0P WRITER: 4 .

d s

l

%' F s

~

. ~ .

.-ww, -. m,+- .--'

60 SUPPORTING DOCUMENTATION OF E0P DEVELOPMENT EPG STEP: C5-6.3 E0P STEP: A0P-0020, Step 5.11 JUSTIFICATION OF DIFFERENCES:

1. Specified reducing service water flow as an alternate way to decrease cooldown rate.

2. This addition is consistent with the technical content of the EPG step.

DATE: '1/14/85' E0P WRITER:

4 -

m I gi b

/

e,' _

m l'

LI.

Attachment 2 RBS E0Ps, Rev. 1 I e f

l L

.~ - -

-u EMERGENCY PROCEDURE - RPV CONTROL i.

TABLE OF CONTENTS

'SECTION PAGE NO.

TABLE I 2 1.0 PURPOSE 3 2.0 ENTRY CONDITIONS 3 l -. l 3.0 OPERATOR ACTIONS 7 FIGURE A 16 FIGURE B 18 ENCLOSURES Enclosure 1 - Full Size Figure A; Heat Capacity Temperature Limit Curve 26 Enclosure 2 - Full Size Figure B; Suppression Pool Load Limit Curve 27 I

1

. -1 1

. 1 1

l. .. l I

t.

. I: . .

e 4

-~ N/ A - _ N/A - l E0P-0001 REV .1 PAGE l'0F 27

. L l l -l 1

._m _ _

?

l TABLE I l l ALARM '

CONDITION / ALARM WINDOW NO. l l I l

I HIGH DRYWELL PRESSURE (P601) 2 (1.68*) Psid/ 2300 l l l MAIN STEAM LINE DIV I, IV l : !

I DIV I, IV HI-HI RAD DR INOP (P601) L 3 X Normal / 2221 l l

l 1 MAIN STEAM l I l

l l LINE FLOW HIGH (P601) l 140% (173 Psid*) / 2033 l

-l l STEAM PIPE TUNNEL l l I

l l AMBIENT TEMP HIGH (P601) l 200*F / 2403 l I

I l MAIN CONDENSER l I l

l l LOV VACUUM (P601) l 11 (8.5*) in. Hg / 2030 l l

I l MAIN STEAM LINE I l l I

l LOW PRESSURE (P601) l 850 (849*) Psig in Run / 2037 l

! l REACTOR VESSEL LOW !

l l l WATER LEVEL I (P601) l -144 (-145.5*) in. / 2541 l I

! I l CRD DISCH VOL HI l l I !

l WATER LEVEL (P680) l 39 Gals / 2176 l l DRYWELL HIGH l l l

I l PRESSURE (P680) l 2 Psid / 2178 l g l REACTOR VESSEL l l I g l HIGH PRESSURE (P680) l 1065 (1064.7*) Psig / 2179 l g l MAIN STEAM LINE l l

! l l HIGH RADIATION l 3 X Normal / 2181 l g l APRM "A" OR "E" _. l l

! l l UPSC TRIP OR INOP (P680) l 15*,/118% / 2161 l "B" OR "F"

l l APRM l l g g l UPSC TRIP OR INOP.(P680) l 15*./118% / 2162 l g l APRM "C" OR "G" l l g l UPSC TRIP OR INOP '(P680) l 15*./118% / 2163 l g g l ARPM "D" OR "H" ,

l l l

g l UPSC TRIP OR INOP (P680) l 15%/118% / 2164 l g l IRM UPSCALE TRIP l l

g l OR INOP RPS CHAN B (P680) l 120/125 / 2149 l g l IRM UPSCALE TRIP l l

g l OR INOP RPS CHAN D (P680) l 120/125 / 2154 ,

l g l IRM UPSCALE TRIP l l l g l OR INOP RPS CHAN A (P680) l 120/125 / 2146 l l l

l IR'1 UPSCALE TRIP l l l g l OR INOP RPS CHAN C.(P680) l 120/125 / 2151 l l g l TRIP UNIT 00F OR l l l l

l POWER FAILURE (4 WINDOWS) (P680) l N/A l l l

l TURBINE CONTROL VALVE l l l g l FAST CLOSURE (P680) l 530 Psig / 2182 l l l

l TURBINE STOP .

', l l l g l VALVE CLOSURE (P680)' l 5% Closed / 2184 l l

] NEUTRON

[ ] l l g-MONITORING SYSTEM'(P680) ll REACTOR PROTECTION SYS TRIP l Various / 2186 l l g l l l l l TRIP LOGIC A OR LO'IC G C (P680) l N/A / 2187 l l l l MANUAL SCRAM (P680) l N/A / 2188 l l g l REACTOR VESSEL l l l l l LOW WATER LEVEL 3 (P680) l +10 (+8.9*) in. / 2180 l l l 1 I I I I I I II I I I l N/A l N/A ll E0P-0001 l REV - 1 l PAGE 2 0F 27 l l l ll l l l

.. . g l 1.0 PURPOSE I l l l The purpose of this procedure is to: I I I I- 1.1 Maintain adequate core cooling. -

t l l 1.2 Shutdown the reactor AND !

l l l 1.3 Cooldown the RPV to cold shutdown conditions; RPV water !

l temperature less than 200*F but greater than 70'F. I I I I 2.0 ENTRY CONDITIONS I I I

~ Entry conditions are ANY of the following:

l CONDITION !

l SYMPTOM l l

[

l 1 l

I 1

I l

I l NOTE l

l l

l l i I H l

l l Conditions and applicable alarm ll l

g l l window numbers are denoted in l g l l Table I, Page 2.

Technical l

l l Specification Setpoint. l l

I I l . I I

l l g

2.1 RPV water level below +10 in. 2.1 REACTOR VESSEL LOW WATER LEVEL 3 l

, ALARM ON P680.

l l 2.2 RPV pressure atove 1065 Psig. l 2.2 REACTOR VESSEL HIGH PRESSURE ALARM g l ON P680.

l I I l

g' 2.3 Drywell pressure above +2 Psig. l 2.3 DRWELL HIGH PRESSURE ALARM ON P680 l j ! l

2.4 A RPV isolation which requires l 2.4 Any of the RED annunciator windows l g or initiates reactor scram. l corresponding to an automatic HSIV l g , l isolation or a condition that would l l require RPV isolation to protect l l

l l the containment or control l l radioactive release rates. l l '

l l 1 l l . I l ,- l I i 1 I I I l '. I I I l . I I I I I

'l I 1 I l- 1 I l ll l l 1 l N/A l N/A ll E0P-0001 l >REV - 1 l PAGE 3 0F 27 l l l l ll 1 I I

m -

u

. THIS PAGE INTENTIONALLY LEFT BIANK

~

-l- , I f

-l

!! 1 l ;

i I

-l l l l

.I I l- 1 I I I I l- l

.l 1

-l l

.I I l- l 1 I I I I I l- 1 I I

-l --

1

-l I i . 1

l -

1

.i I l- I

l 1 l I I I ll , I

l l 1 I l I l' i 1 < l I I li

_ fl.I l

I l

.I . 1 I .

I ,. I I I

'l .

1

.. l - l

.I '; I l- l l I l- 1

-l I l- I l i I 6 1 -

l ll l l l l 'N/A l N/A .ll E0P-0001 l REV - 1 l PAGE 4 0F 27 l

-l l ll l l 1 m_

NJ l I l CONDITION SYMPIM l l -l l 2.5 A condition which, requires 2.5 Any of the RED annunciators (on i I reactor scram P680) that correspond to an auto- ; I l AND reactor' power is above 5%.

matic or manual scram signal I l AND APRM's or IRM's indicating l T

l l greater than 5% power. l I l l

I l _ 2.6 A condition which requires 2.6 Any alarms in (2.5) l reactor scram AND no reliable indication on ARPM, I I AND reactor power cannot be IRM or SRM. I determined. l I I I I l I I I I I I I I I I I I I I I I I I 1 I . I I *

-l I l l , I i 1 I l I I I I I I I I I I I I l < l l I I

l I i I ,

I I 1 I . I I ,. I I I I I I I I '. I I I l . I I I I I I I

! I I l

l l I I ll l REV - 1 l

PAGE 5 0F 27 l

l N/A l N/A ll E0P-0001 l l l l l ll l l l

M l [ NOTE 1] I I I l If control rods are not inserted beyond ((06)) by the reactor 'I l scram, then the operator must exit this procedure and complete I

-l AOP-0021 before returning to this procedure. At that point, ; I l power control predominates the operator action; RPV level and I pressure are controlled as dictated by reactor power. The g l operator must closely monitor containment parameters and enter g

l E0P-0002 (concurrently with A0P-0021) as entry conditions are I reached, g g

i l i I I I I I I I I I I I I I I I I I I I I I I I I I l l l . I I '

I I I I - 1 I I I I I I I I I I I I I I I I I < l l I I I I I I . I I I I . I I I I I I I I I I . I I I I I I I I I I I l l I I I I il I I I l

N/A l N/A ll E0P-0001 l REV - 1 l PAGE 6 0F 27 l l l ll l l 1

b 3.0 OPERATOR ACTIONS l l

l I l Irrespective of the. entry conditions; execute the following 'l l concurrently: l l :l l MONITOR AP CONTROL REACTOR POWER PER SECTION 3.1. l I I I MONITOR AND CONTROL RPV WATER LEVEL PER SECTION 3.2. l I I l - MONITOR AND CONTROL RPV PRESSURE PER SECTION 3.3. l l 1

1. INSTRUCTIONS l CONTINGENCY ACTIONS I I i 1 l 3.1 MONITOR AND CONTROL REACTOR POWER I I I I l 3.1.1 IT a reactor scram has not beenl I l Eitiated l I l THEN initiate a reactor scram. l !

l l l l 3.1.2 Confirm or place the mode l I I switch in SHUTDOWN. I I I I I I 3.1.3 Confirm that all control rods l C3.1.3 IF all control rods are not !

I are inserted beyond position l Eserted beyond position ((06)) I l

((06)). . l THEN proceed to A0P-0021 I l I l [ NOTE 1].

I l l

1 3.1.4 Enter A0P-0001 and perform !

I concurrentl procedure. y witti this g

I I I I I I I I I I I I I I I l i '

I I I I I I .

I I I I .

I I , I I I

!. . I I l l .

I I I I I I I I I I I I I I I N/A N/A E0P-0001 REV - 1 PAGE 7 0F 27 I I ll l 1 I.

l [ NOTE 2] l l 1 l RPV water level can be monitored on the 'l l following instruments in the Main Control I

l Room. ; I I . I l INSTRUMENT NUMBER PANEL TYPE / RANGE I I I i 1B21-R605 P601 Shutdown /0 in to 400 in l l 1B21-R623A/B P601 Wide Range /-160 in to +60 in I I IB21-R604 P680 Wide Range /-160 in to +60 in I I IC33-R608A P680 Narrow Range /0 in to +60 in I I IC33-R608B P680 Narrow Range /0 in to +60 in I l IC33-R608C P680 Narrow Range /0 in to +60 in l l IC33-LR-R608 P680 Narrow Range /0 in to +60 in I i 1C33-LR-R608 P680 Upset Range /0 in to 180 in !

l 1B21-R615 P601 Fuel Zone /+50 in to -150 in* I I 1B21-R610 P601 Fuel Zone /+50 in to -150 in* I I I I *0 in, reference is top of active fuel. I I I I If none of these instruments are operable !

I then use other sources of RPV level such I l as alarms, trip units, computer, local I transmitters.

I I I I I I l 1 I I I I I I I I I I I I I I I i l <

l i '

I l I I I I . I i 1.

l . I I .- 1 I I I I I I I . I I I I I l I l- I

'l I I I I I N/A N/A E0P-0001 REV - 1 PAGE 8 0F 27 I I il l I I i

1 I I l INSTRUCTIONS COEINGENCY ACTIONS l

.i l ~l I 3.2 MONITOR AND C0!GROL RPV WATER LEVEL [ NOTE 2] I I I rI I 3.2.1 Confirm initiation of any of l C3.2.1 IF any should have initiated l I the following^: l but did not, I

-l l THEN manually initiate. I I Reactor Scram l l l l l l RPV Isolation l I I I I l ECCS I I I I I

Emergency Diesel Generator i l i I I I I I I I I I I I I I I I ~'

I I I I I I . I I I l I I I l I I I I I I I I I i l i I r l l

l '

I l 1 I I I I l l I . I I I I I I I I I I .

I I I I I I I I I l' I I I I I N/A N/A E0P-0001 REV - 1 PAGE 9 0F 27 l l l ll 1 1 I

... 9 l CAWION #1 l l l l Do not permit low pressure ECCS injection not "I l required for adequate core cooling (from 2 Psig I I drywell pressure) while depressurizing. II I I f

I I l' CAWION #2 I !

l- 1 I Do not secure or place an ECCS in MANUAL mode unless, by at least I two independent indications, (1) misoperation in AWOMATIC mode is I. confirmed, or (2) adequate core cooling is assured. If an ECCS is g I placed in MANUAL mode, it will not initiate automatically. Make

~

l frequent checks of the initiating or controlling parameter. When y manual operation is no longer required, restore the system to l

STANDBY mode if possible. g g

i I CAWION #3 Do not throttle RCIC below 1700 RPM.

I I

CAWION #4 g

l If suppressio,n pool water level increases to 20.4 ft (+.4 ft l indicated) or if CST level decreases to 2 ft 4 Sf 8 in., then l l l

confirm autonfatic transf er of HPCS and RCIC suctions from the l

-l CST to the suppression pool. If necessary, manually initiate l as follows: .

l- l_

l- l HPCS; open E22-MOVF015, close E22-MOVF001 l l

RCIC; open_E22-MOVF031, close E22-MOVF010 l l

.I l 1 l-l- [ NOTE 3] l l 'l l

It is the intent, here, to complete the requirements of E0P-0005 l

j. or AOP-0021 (as, applicable) before proceeding further in Section l l

3.2 of E0P-000h l

-I .

I l- < l I I I . 1

-l- c I I I I I 1 I i '. I

=l I l l

'I I

'll l I I l' '

l l I I I -11 1 I I l N/A l ~N/A ll- E0P-0001 l REV - 1 l PAGE 10 0F 27 l 1 1 11 I I I

G

-l '

l l INSTRUCTIONS CONTINGENCY ACTIONS I l

y .................................................................................'l l

.... .................! .g g {gNS f} y2, f}, M yp,,,,,

II {

l . I l

l 3.2.2 IF while executing step 3.2.3 l

l l

l M.

l [ NOTE 3] l I l l !

l 1. Boron Inject is required I I I THEN proceed to A0P-0021. l I I l l

l 2. RPV water level cannot be !

l I determined I l

I THEN proceed to E0P-0005. !

l l 1 l

I 3. RPV flooding is required I l

I ([ NOTE 5]; Page 20) l THEN proceed to E0P-0005. l g

I- !

I

-3.2.3 Restore and maintain RPV water l C3.2.3 IF water level cannot be

~

level between +10 in and l restored and maintained between I I

+55 in, with one or more of l +10 and +55 in.

the following system: l THEN maintain RPV water level

l above -160 in.

l I

1. Condensdte/Feedwater l 1. I.F ADS timers initiated l l g

(preferrpd) l AND RPV level can be l

g l maintained above -160 in. g g

l THEN prevent automatic RPV l

g l depressurization by resetting l

l 1 the ADS timer.

l l I I

2. CRD l 2. IF RPV water level cannot be g l

g a. Operate two pumps if l maintained above -160 in. g g possible l THEN proceed to E0P-0004 l

l b. Increase flow rate to l " Level Restoration". l maximum. l l ' l l l l

l

3. RCIC l l

l l l

l

4. HPCS -

l l

1 - 1 I

l S. LPCS ,

l g I I I

l

6. LPCI l l

l l 1 I l- I

-l . I I I l' I I I I I I I I I ll l l l l N/A l N/A ll E0P-0001 l

REV - 1 l PAGE 11 0F 27 l l l ll l l l

r-- . ,.

-g i-

-[N01T 4]

RPV pressure can be monitored on the

-following instruments in the Main l l

y v1 . Control Roem. g aNEL TYPE / RANGE IC33-P605 P680- Wide Range /0 - 1200 Psig

~g iC33-h609 P680 Narrow Range /850 - 1050 Psig l g :t Si-R623A/F P601 Wide Range /0 - 1500 Psig l g

01 9602 P601 RCIC St. Press /0 - 1500 Psig l l l l l

.I- I 1 1 1 I I I l- I 1 I l- 1 I I l- I

'l' ..

l g l

-l . I I '

I l l l ,

I I I I I

.I i l l 1- I I I l I I I I < l l I

-l .

I I ~

I l

l l I l

ll. .

,. I I I

,1 1

,l. , l l . I I i 1 . I I l' l I I I I I 1 l l l 11 1 I I-l *A I - , Il 6..?-0001- l REV - 1 I PAGE 12 0F 27 l l l Il l I I

~ ~ -

1[I Y "'

g' '

\

INSTRUCTIONS C0ffrINGENCY ACTIONS I h-i 3.2N EN specified in Section 3.3 C3.2.4 IF RPV can no longer be cooled

' proceed to normal shutdown down by depressurization ' l l '

g procedures,(GOP-0003 or 0004) '

AND ;

g as applicable. _

j g g l 1. RHR shutdown cooling n. ode g g l cannot be established ;

I I l l 2. RPV temperature must be 1 l l reduced and/or the RPV must g g

l l be maintained in a cold g l l shutdown condition g i I l

l l 3. Control rods are inserted y

] l beyond position ((06)). g i I l l THEN proceed to A0P-0020 l l g l " Alternate Shutdown Cooling". g I

I I I I I I i .

I l l 1 -

l I l I I I I l l l l l l l l l l l l I l I

l -

l ,

l l l l l 1 l I l I - I I .- l l

l l -

I I I I I I I I I l l l

N/A N/A E0P-0001 REV - 1 PAGE 13 0F 27 l l l ll l I

CAtTTION #5 Cooldown rates above 100'F/hr may be required to accomplish this step.

I I CAtTTION #6 I I g Combinations of temperature and level denoted l g below may render the level instrument inoperable. l l 1 I I lTEMPELEMENT/l INDICATED l LEVEL INSTRUMENT l l LOWER TAP l

-l l l l* TEMPERATURE LEVEL l TYPE RANGEl NUMBER ELEVATION l l l l' l I I l

~l l l l Shutdown 0 in. to +400 in. **lB21-R605](LATER) in. [

l l l l (Indicator) l l [

l l I I I I i I l l (LATER) l (LATER) l Wide Range -160 in, to +60 in. lC33-R608l(LATER) in.l l l l l l (Recorder & **lB21-R604l(LATER) in. l l l l l Indicator) l l l l l l l I I I I l l (LATER) l (LATER) l Narrow Range 0 in. to +60 in. (C33-R608l l l l l l l (Recorder & **lC33-R608l(LATER) in.] l l l l l Indicator) l A, B, Cl l l l l 1 1 I I I I l ~l (LATER) l (LATER) IUpset Range (0 in. to 180 in.) lC33-LR- l(LATER) in.] I I l l l **' R608 l l l l- 1 I l I I l l l l l , l Fuel Zone +50 to -150 in. ***lB21-R615l(LATER) in.l l l l l l (Recorder & lB21-R610l(LATER) in.l l l l l l Indicator) l l l l l *Drywell area temperature (M71); average the two points. 1

[ -**0" reference is 15 in, above bottom of Steam Dryer Skirt; 162 in. above TAF l l ***0" reference is TAF; 147 in, below bottom of Steam Dryer Skirt. l I I I I l CAITTION #7 I I , I l Do not throttle RCIC below 1700 RPM. l I -

l I I l ^

CAUTION #8 l

,I -

1 l Do not depressurize the RPV below 50 Psig unless motor driven pumps suf- l l ficient to maintain'RPV water level are running and available for injection. l l l I I I I I .

I I I I . l l l l l l- l 1 I I I I I 11 1 I I I N/A l N/A Il E0P-0001 l REV - 1 I PAGE 14 0F'27 I I I ll l I I

u

.I I I !

INSTRUCTIONS C0!GINGENCY ACTIONS I l 3.3 MONITOR AND C0!GROL RPV PRESSURE. [ NOTE 4,' PAGE 12]

l ....................................................................... l

......... ...........! . CAgggg , #p y , yp g , q? , M yp ,

I I I I l

l 3.3.1 E a reactor scram has not beenl l initiated l l l l

THEN initiate a reactor scram. l l I I l

l 3.3.2 E any SRV is cycling l C3.3.2 E no SRV is cycling l THEN manually open SRV's until l THEN continue with instructions l

l l

RPV pressure reduces to l 3.3.2.1.

l 935 Psig. l l l l I I l

1. IF Emergency RPV l 1. E boron injection is l l

Depressurization is l required l l

anticipated ([ NOTE 7]; l THEN proceed to AOP-0021 and l l

Page 20) l continue concurrently in this l l

AND boron injection is not l procedure at Step 3.3.3. l l

required l l l

THEN rap-idly depressurize l l l

with the main turbine bypass l l l valves. l l 1 I I l 2. IF Emergency RPV Depres- l l

[ surization or RPV Flooding l l l is required ([ NOTE 7]; l l l Page 20) l l l AR less than 7 SRV's are l l l open l l l THEN proceed to 3.3.6 l l l " Emergency RPV l l l Depressurization". l l l < 1 1 I 3. E RPV FLOODING IS REQUIRED l l ([ NOTE '7]; Page 20) l l AND at least 7 SRV's are l

1 OPEN l l l THEN pr6ceed to E0P-0005 l l "RPV Flooding". l l- '.'

I I I I I I -

1 I . I I I I . l I I I I I I i i l l I i 11 1 I I l N/A l N/A ll E0P-0001 1 REV - 1 l PAGE 15 OF 27 l l l ll l l l e

y..

~ :-' y A Y.

.,..3 -

) 4. ".;- .

W i I I

l h{ I l ! th ,'h

'; 'ill. ll !

l .

l t l!!l!

NEAT CAPACITY TUPUIRTURE Liitti 'l u==rtMu ,sas i i l' ! '. I !

! ! lil i l l i

'! ! l i l l 1 I l i ll' i j l l

. . l

, l;. ,.

L .

I l I

'l i

i ,,,

ii

,,... .... i l.

l l. l ,I ,. , ,

i 1

l[

I l [

T"d

?.. I l '

l l ll !

d l

l:!

i i; --

I

! l i ;

I see '

l' ,

I I ! i n i I

l ji' icc'ertAsr.s' seus I

[ ise '

i lf l

l 1** :

I I l

I l

l l l !

I l

l l < -

_ l I l I

o I l :

' o a .: *

-l l ,

, < c

y. C. l l 6 , '-

,1 -

l ' ;$;-

ies } I! ' {} l ' -l l '-

I

e sa i = > *as = ree ese =

i.e. ee iss , asse . l

are re==. <,.ae l

l I

[ [ NOTE 5) l 1 I l Figure B is on Page 18. l l l l l l CALTION (19 l 1 I

[ Cooldet.n rates above 100*F/hr may be required to accomplish this step. I i

i l i I l CALTION /k10 l 1 I l Observe NPSH requirements for pumps taking suction l l from the suppression pool. (NPSH limit curves (LATER)). l l 1 l .

I I I

~l 1 I I i l I i i l l I I I I I I I II I I I l N/A l N/A ll E0P-0001 l RIV - 1 l PAGE 16 0F 27 I l l ll l l l

u

-l l ll

! INSTRUCTIONS 1 CONTINGENCY ACTIONS I I I 3.3.3 While performing Step 3.3.4 I C3.3.3 l

1. Maintain suppression pool 'l y 1. I_F the suppression pool l

g temperature in the ! cannot be maintained in the l

-g acceptable zone of the Heat- '

acceptable zone of Figure A l g Capacity Temp Limit in - or Figure B (Page 18) l l

Figure A and suppression l THEN maintain RPV pressure l g pool level in the acceptable l below the limit.

l l

zone of the Suppression Pooll l

Load Limit of Figure B l l l

[ NOTE 5].

l . :. ; ;. :. : ; ;. :. :. ; ;. :. :. ; ;. :. :. : : ; ; ; ; :. . :. ; ;, :. :. :. :.****:.

l l

.. :. :, :. :. :. :. : :. ; ;. :. . .r* :. . :. ; ;. : :. :. ; ;. ;. :.****

l l' ----- - -- -

SEE CAITTIONS #9 AND #10

:. : ; .. .. .. . :. ; ***** l l

l I I

,l 2. E RPV water level cannot bel 2. E any injection subsystem l

-l determined l or alternate injection sub- l

_l OR has decreased to -160 in.l system becomes lined up for l l AND no injection or l injection with at least one l

-l alternate injection sub- l pump running, proceed to l l system is lined up for l Step 3.3.6. l l injection. (No lined up l l

.l subsystem has at least one l l l pump running.) l l l THEN when RPV level drops .l l l to -111,in. on Fuel Zone l l l Instruments OPEN ONE SRV l l l WHEN RPV. pressure drops l l l- below 700 Psig, proceed to l l l Step 3.3.6. l l.

1 -. . .

l .

I

l 3.-E boron' injection is l 3. E low water level MSIV l

-l' . required l interlocks must be bypassed, l l AND the main condenser is l THEN complete contingency l l available , l action detail (LATER) to l

_l AND no fuel failure or steam l bypass these interlocks. l l line break is indicated l l l~ THEN open MSIV's to l l

.l reestablish the main l l

-l_ condense'r as a heat' sink. l 1

-1 I I '.' I I I I: -

I

*l - .l l ~

1

.I l I , I I I

~l l I- I l' I I I I i 11 I I I l 'N/A l N/A ll E0P-0001- l REV - 1 l PAGE 17 0F 27 l

-I I -ll l l l

r-2 r

l I CAWION #11 c l_ l I Do not depressurize below 50 Psig unless motor driven

!- pumps sufficient to maintain RPV vater level are run-g

.ning and available for injection. g

~1 I

[ NOTE 6j It is the intent to give the operator a wide control band to g eliminate unnecessary actions that would be required for a l g narrower band, t.m.evar, the operator should minimize rapid l

.g depressurization/cocidown rates and should attempt to main- g

g. tain RPV pressure aleve RLIC Isolation Setpoint (50 Psig). l

l. = - . . . _

l l' CAUTION #12 I

g- l l l g Do not open SRV's if supression pool indicated l p l water level is below -14 feet since the "X" l quenchor would not be submerged in water.

l l l l

' ~l i

j. CALTTION #13 l 1 --

l

_l Do not throttle RCIC below 1700 Rpm. l

'l I I I

, l ,

CAUTION #14 l l l l; Do not use RWCU if boron has been injected. l l l l- 1

-l FIGURE B l

.1- - .I l' ~ Suppression Pool Load Limit Curve. I I l r -l' ,

1 I '

I l1 .

['

l: I "I I 1, I 1 I

3 .-- .l

' ;i:

[

l '

l l . _l I 11 3

1 I

,l~ ,, I g-

.I l l- l 1: I L

l l

' l-- I -11 I .I I l .N/A l <

N/A 'll -E0P-0001 .I REV - l' l PAGE 18 0F 27 l il

- 1. I l I I r

~

l l l ]

INSTRUCTIONS CONTINGENCY ACTIONS l .. .............................................................................. l l l l

............... ......... SEE CAU{ IONS #11 AND #12 ,,. . ,,, ,,,,,,

, ,,,, , ' l I I l

l 3.3.4 Control RPV pressure below l C3.3.4 E additional pressure relief l 1033 Psig with the main turbinel is needed [

l bypass valves. l THEN use one or more of the j

[

g l following [ NOTE 6): l I I l

l l 1. SRV's - cycle in the l l following order l l

l ',

l E suppression pool indicated l l ~~~

l water level is above -14 ft. l l l l l l a. IF SRV pneumatic supply is l l l or becomes unavailable l l l THEN depressurize with l l l sustained SRV opening l l l l l l _ [1B21-RVF051G] l l l [1B21-RVF047B] l l

l _ [1B21-RVF041L] l l

l _ [1B21-EVF041F] l l l [1B21-RVF047C] l l l [1B21-RVF051B] l l , l _ [1B21-RVF041G] l l l _ [1B21-RVF051D] l l -

l [1B21-RVF041B] l l l [1B21-RVF051C] l l l [1B21-RVF047D] l l l _ [1B21-RVF047A] l l l [1B21-RVF047B] I l l [1B21-RVF041C) l l l _ [1B21-RVF041D] I l ....... ...... .......

, l

. y.,,,

_ [1B21-RVF041A] ;.;,

l l

l . SEE CAUTIONS #13 AND #14 I

.m; , ;.;,, ;;,.;;;;;;;;;; ,

l l l l

2. RCIC l l I I I I l ', l 3. RWCU l l l I l l 4. Steam Line Drains l l l l l '

l S. Other steam driven equipment l l l I I I I g l 1 I I I I I 1 I 11 I I I l N/A I N/A 'II E0P-0001 I~ REV - 1 I PAGE 19 0F 27 I

'l I ll l l 1

_ ~

! I CAtTTIGN #15 I I Do not depressurize the RPV below 50 Psig unless motor driven pumps suf-ficient to maintain RPV water level are running and available for injection.

l l l CAUTION #16 Cooldown rates above 100*F/hr may be required to conserve RPV water inventory, protect primary containment integrity, or limit radioactive l l l

release to the environment. l l l

[ NOTE 7) i I l

Emergency RPV Depressurization is required when: l 1 l l

- RPV flooding is required and less than 7 SRV's are open (EOP-0001, Step l l C3.3.2.2). l

-l - Suppression pool temperature and RPV pressure cannot be restored and l l

maintained below the Heat Capacity Temperature Limit (EOP-0002, Step l l C3.1.4). l l

- Drywell temperature cannot be maintained below 185*F (E0P-0002, Step l l 3.2.1). l l

- Suppression pool. water level cannot be maintained above the Heat l l

Capacity Level Limit (EOP-0002, Step 3.5.2) or below the Suppression l l

Pool Load Limit '(EOP-0002, Step C3.5.3). l l

- Secondary containment temperature, radiation levels or water levels l l exceed the Maximtp Safe Operating Limits (EOP-0003, Steps C3.1.7, l l C3.2.5 or C3.3.5). l l - RPV pressure is too high to permit available injection systems, l

l injection subsystems or alternate injection subsystems from injecting l l adequate flow into RPV (EOP-0004, numerous s;eps). l l .

I l RPV_ Flooding is required when: l l l l - Temperature near the cold reference leg instrument vertical runs l l exceeds the RPV naturation lim 4t. l l - RPV water level cannot be determined. l l - Containment to annulus differential pressure cannot be maintained below l l 15 Psid or drywell to containment differential pressure below 25 Psid. l l - Drywell temperature cannot be maintained below 330*F.

l I

1 I I i -

'.' l l l 1 1 I . I I ~

l I l l .

I I I I I

-1 I I I l_ l i l 11 1 I I l N/A l N/A ll E0P-0001 I REV - 1 l PAGE 20 0F 27 l l l ll l l 1

l 1 l

I INSTRUCTIONS I l CONTINGENCY ACTIONS I 1 l

l ..... ........................................................................... l .

I SEE CAITTIONS #15 AND #16 -

l ................................................................

I 1 I 3.3.5 WHEN RPV water level is l C3.3.5 IF the reactor is not shutdown l

_g stabilized l while executing this step, l g

AND all control rods are l THEN return to Step 3.3.4 and l

y inserted beyond position -((06))l continue until the reactor is l y

OR l shutdown l

l I

I

1. RPV water level is l

stabilized l

1. IF the entiro contents of the l SLC tank has not been y l j g AND the entire SLC tank has l injected into the RPV l

l been injected into the RPV l THEN determine that at least l l

OR l 618 lbs of boroi has been l l l injected into tTe RPV per l

2. RPV water level is l (LATER).

l l l

stabilized l l l AND the reactor is shutdown l l l

AND no boron has been l l l

injected into the RPV. l l l .. I I l

THEN depressurize the RPV and l l l maintain cooldown rate below l l l 100'F/hr. . l l l l l l 3.3.6 IF Emergen(y RPV l C3.3.6 l l Depressuriz.ation is required l l l [ NOTE 7] l l l THEN perform the following: l l l 1 l l 1. E boron is injecting l 1. IF boron is not injecting l l THEN before depressurizing l THEN proceed to Step 3.3.6.2. l l terminate and prevent all l l l injection into the RPV l l except boron and CRD. ' l I .

I I I I I I I I I I 1 e

I l I I I . I I I I 1 I I I I I I I I I I I I I I ll l 1 I l N/A l N/A ll E0P-0001 l REV - 1 l PAGE 21 0F 27 l l l 11 I I I

l [ NOTE 8]

l Use in'the order which will minimize radioactive I release to the environment. See (LATER) for bypass I- details. -

l

-l l CAUTION #17 Do not use the RHR steam condensing mode unless (1) the suppression pool temperature can be l

maintained below 155'F and (2) more than one RHR l loop is available.

g l l l l l l l l 1 1 I

.I l l l l l l 1

~

-l I l I l- -

I l _. .

I I I l-

.l l , I 1 - I l .

l

.l 1 1 I l- 1

-l l l l l- l

l ,

I

.l- -l l- ,

, I-

, -- l . I l I

.l l l !

.l .- ,

I l 1 l

.i . ..

l .- l I I l , l l -1 l- I l

I I I

-l 1 l I' I I 11 I I I l N/A l N/A II E0P-0001 l REV - 1 1 PAGE 22 0F 27 l l i II I I I

l I .

I INSTRUCTIONS CONTINGENCY ACTIONS .

l 1

2. H available, open all

.- turbine bypass valves. '

+ . ;. ;. :. ;. :. :. :. ;. ; :. :. :. :. :. :. :. :. ;. ;. ;. :. ; :. :. ;. :. ;. :, ;. ;. :. ;. :. :. :. :. ; . :. :. ;. : :. :. :. ;. :. :. ;. ;. :. ;. ;. :. ; :. :. ;. :. :. **:. :. :. :. :. :. :. . ;, :. ; :. :. :. ;. ;.-l g SEE CAUTION #17

. ; ;: . ;. :. ;. :. :. :. ;. :. ;. ;. :. :. :. :. ; :. :. :. ; :. :. : :. ;. ;. ;. ;. :. :. :. :. :. ;. :. :. ;. :. ;. :. ;. :. :. :. :. ;. :. ;. :. :. ;. ;. :. ;. :. :. ;. :. :. :. ; :. :. :. :. :. *********** l l l 1 g 3. IF suppression pool 3. IF suppression pool indicated l l l

indicated water level above water level is not above l

-14 ft. l -14 ft.

l l THEN open all ADS valves. l THEN rapidly depressurize l l l l the RPV using: [ NOTE 8] l l l _ RCIC l l l RHR (Steam Condensing) l l l _ Main Condenser l l l ___SJAE l

~l _ Steam Seal Evaporator l l Main Steam Drains l l l _ RPV Head Vent j I I, l IF all ADS valves cannot be l l l opened l l ,, l THEN open SRV's until a total l l of 7 SRV's are open. l l 1

-l 4. Monitor.RPV water level l 4. IF RPV water level cannot be l l '

l determined l l l THEN exit this procedure and l l . l complete E0P-0005 "RPV l l- l Flooding". I

1. l l l _ S. Maintain containment 5. IF containment parameters l l parameters as follows: cannot be so maintained l l _ Containment to annulus THEN exit this procedure and l l- differential pressure below complete EOP-0005 "RPV l l 15 Psid Flooding". l l _ Drywell to containment' l l differential pressure below l l 25 Psid l l Drywell temperature below l l l 330*F l l 1 I i l e

I i I I I I I I I l

. l l

'l i 1 I

.I l l i I I I I ll 1 I I l N/A l N/A ll E0P-0001 1 REV - 1 l PAGE 23 0F 27 l l l ll l l 1 L

a CAWION #18 I If continuous LPCI operation is reqaired to assure adequate core cooling, do not divert all RHR pumps l

g from LPCI mode. Leave at .1. east one RHR pump in the l

LPCI mode.

g l l 1 CAWION #19 I I I I g If boron has-been injected and all control rods are j g not inserted beyond ((06)) then the RPV level must l

.l be maintained below +55 in. while using Shutdown l

-l Cooling mode of RHR to prevent excessive dilution l of the boron solution.

l- l l I I I l' I I I I I I I I I

.I -1 l --

l 1 1 l; ,

l I I I , I I . I I - 1 I I I 1 I I

'l -

1 I I I I I ,

I I I

.I ., I I I l- l l .

I

-l .

I l- .- ,

l.

I I

.I :l l l 1 I

g. l l .I I I I I

1. I

~l I I I 1 I 11 1 I I

~l. N/A l N/A ll E0P-0001 l REV - 1 l PAGE 24 0F 27 l l l l1 I I I

l l l: INSTRUCTIONS I C0brTINGENCY ACTIONS !

l l l l

l ....................................................... ......................... l I

SEE CAtTTION #18 AND #19 l = = = = = = = = = = = = :. = :. :. = :. = :. :. = = u u :. = :. u . = :. u = = u ;. :. :. :..I I I 3.3.7 WHEN the RHR shutdown cooling C3.3.7 E the RHR shutdown cooling mode interlocks clear (at 135 Psig l cannot be established g

RPV pressure) l AND g THEN initiate the shutdown l further cooldown is required l l cooling mode of RHR. l THEN continue to cooldown using l l

g l one or more of the systems l g l used in Step 3.3.4.

l I I l

_ L.3.8 Proceed to normal shutdown l C3.3.8 IF RPV can no longer be cooled l l

procedures (GOP-0003 or 0004) l down by depressurization l l

as applicable. [ AND l l

l 1 l

1. RHR shutdown cooling mode l l

l cannot be established l l I l l 2. RPV temperature must be l l l reduced and/or the RPV must l l _

l be maintained in a cold l l l shutdown condition l 1 I I l . l 3. Control rods are inserted l l l beyond position ((06)) l l I I

[ '

l THEN proceed to A0P-0020 l l l " Alternate Shutdown Cooling". l l l l '.'END OF E0P-0001" l l I I I I I I I I

'l I ,

I I I

-l l l ., I l

I I .- l l f I I I i .

I l .. I l 1 I I l I I I I I I l 1 I I I ll 1 1 I l N/A .1 N/A Il E0P-0001 1 REV - 1 l PAGE 25 0F 27 I I I II I I l

g.- q..,

W ?'-

9 ->

ENCLOSCRE - ! FULL 5IZE FIGURE A; HEAT CAPACITY TE"PERATURE LI.'!IT CCR*/E -

! g. . . .

l r

= l

l i E I

l iC I ,

I .

I gy- l

[ [) g,L 9

8; W. :.

l \

~.

l .

9 l I l l - =p . 2.:- -l

= \

l . -

l - +

l 1 l i

l --

5 ,

i I l I : .. I

l l l l

l l

I I

_I I

l l 1 I -

l l l l

l l

1 I

l l l

l I

. l l

s a n a a ! l l

w -m m m .

. l l

l ll l l l ENCLOSURE - 1 i PAGE 1 0F 1 ll E0P-0001 REV - 1 l PAGE 26 0F 27 l l ll l l

Q d.sM W~&

, . . , . -- v

" ~

Ww

~

fl e

I

% '{

! er' . .-

l . i(p. =l I

ENCLOSCRE - 2 FULL SIZE FIGURE B: SUPPRESSIGN P00L LGAD LI.MIT CCRVE t

i. 2., -

-~

i ,,,,,,,,, ,_ : g---------- l<

e i * ::

g. =

h.m . e. __ _

4 i ,j ,,;, ,,;;,;; '

c:l= . ::: , - - - - - - - - % >

.- . 5 = := ;- : : -- '

-:a.

l' -- -

l .

l g .- .. _

_ __- _n_:n .

l i .. . _ . ._.. . . . .___ _ = = l l .. 9.o - .I - . _

_

.. -. *==.- .. _

6 l ..

I

-a

- : -- " : : : I j l i 2 15 :' -

E. 7 I

, l :.. ; E -"

=

3 ::.r- .:

l _ E l

': . . "4". -

=: - --' - '-

l .- ; : : l

. . ?. .

i l . .. . .- i l 3 $- - - - - _

b s.. !

I - -

al =*=== == = = = :3: = = = = = = = -- l l . _ .

=-

r :_r -- - - - -

+d:

= = = = = = -

= = =- = .= = ..J 1. .

i -- - +-~, "

El.i _ _ L.,

r l Z _r,

I l =,= ;* '; t. .* -

=l" . f" - ' .. . -

-_S

-: 3.

I .. = 2 ,. ... - _

.. . l ._ _ . _ .o s

l ._ :: .t. ; .

.r. :-1 --+-- -- - **- -

E E ,,

I Cu I t.

,. , ,,i "-I*E. F--- = - '

-E .,E I r=i.. J.E l ,.

l l .:_ ...: . .

l

- : _--f=_ _ c= .f.3 _

l i -

.=.: :::- ,_' .: -: 3.- ".: : E' i l ..

. . . . . . .- b.' . . . ..= l -

.r" . ~ . .

-- ._= =

3 I I :;; .g ;

g* *_*f.f.g

g .

I -.. . . . . , _ . .

Q ;. _. _* " "'

'l l -._ _ _ _ _ . . . .. ._. _ .

: l E

l _

==L._ . . . E . . ..

i l ._,,.- l: l:' _-

l l

. ...1._

l

_ 4 . . .

l : :

l

. =4 _. l l =_:=-_-

- : : I s_.

i . . . .

l l -

= i i-i-

E

\

l l

[ :u:. .- r E E l

~

l -

_ Ei i l l

. . e .

g l

~

f. .

8

m. -

. W m

=

. a M

.}

- - . - - - - . . - - 5:3" l l E W E= M ml = El=ll ::: Elll:i ~

B:= IR= B:ll: M M M M e- ' sN.

El I I l . . . . .o . . . . -l

ae +i et e

.e e e . . .-*

I I

I .+ + 4 + + + + + + a e

- (*359,,

Teams aegegg teog noteseg yogeogsg i , l:

I 1 ENCLOSURE - 2 PAGE 1 0F 1 l E0P-0001 REV - 1 PAGE 27 0F 27

I i

+ - - - + - - - - - , . - - - - .. n,,n_

. ~

u g l

l EMERGENCY PROCEDURE - PRIMARY CONTAINMENT CONTROL l l

l 1

TABLE OF CONTENTS l l

SECTION- PAGE NO. I i

1.0 PROCEDURE 3 l 2.0 ENTRY-CONDITIONS- 3 3.0 OPERATOR ACTIONS 5 l

FIGURE A 6 TABLE A 8 Ii FIGURE B 10 1 TABLE B 12 ~

l

FIGURE C 16

' FIGURE D . 18 FIGURE E 20 a

! ENCLOSURES (fi- } ; Enclosure 1 - Full Size Figure A; Heat Capacity Temperature

'I L Limit Curve 22

'? < 1 - Enclosure 2 - Full Size Figure B; RPV Saturation Temperature 1,~~ Curve 23 Enclosure 3 - Full Size Figure C; Primary Containment Pressure l Limit 24 Enclosure 4 - Full Size Figure D; Heat Capacity Level Limit 25 Enclosure 5 - Full Size Figure E; Suppression Pool Load Limit 26

-l

.I .

l 1

0 0

5- l l

l I N/A' N/A E0P-0002 l REV - 1 PAGE 1 0F 26

N

'l THIs PAGE INTENTIONALI,Y IEFT BLANK I 1: I l- I

1. I

'l-

.I

1. > 'I '

I I I

.l. 1

' l-- I I

.l. ,

I i LI '

I 71-l- I

-l I 1 1

'l l I I

-l I

.l I

-l I

-- l - I

-l 1

'l I if '

I l

,l I

1. _

l l

l

-1 , I g- . l-

-l l-

l 1 :

-l- I

'l I i l- 1 l I i l I , I l: .I l

- :l .

I. I 1 .

l

l. *'.

l' I

- 1:l! ,.

1 l ,,.1 I

-1 ^ '

. I l-

.l . - l

-1; . l

.,1 , I l

il l7 l 1, 1 I

1

.I I

I l. ll l- 1 I

-l;: -N/A-'l' N/A. ll E0P-0002 -l REV - 1 l PAGE 2 0F 26 l

-:1 'l ' - Il l I I

g Il l !l I 1.0 PURPOSE l

l l 1.1 To maintain primary containment intact. 'I i I :

l 1

I 1.2 To protect equipment in the primary containment. ;Il l

l 2.0 ENTRY CONDITIONS l

l I

l Entry conditions are any n of the following:

I I

SYMPTOM I l CONDITION l l

I l l _ 2.1 Suppression pool temperature 1 2.1 SUPPRESSION POOL TEMP NORM MAX I

I above 95'F. GREATER THAN OR EQUAL TO 95'F Alarm on P8087 I 2.2 Drywell temperature above 145'F. 2.2 DRWELL AMBIENT HIGH TEMP alarm 1 on P601.

I 2.3 Containment temperature above l 2.3 CTKr TEMP HI alarm on P601.

90*F.

2.4 Drywell to containment l 2.4 HIGH DRWELL PRESS alarm on I

OR containment to annulus P601.

3Ifferential pressure above

'g 2 Psid. ,

g 2.5 Suppression pool water level , 2.5 SUPPRESSION POOL LEVEL HIGH g

above 20.0 fget (0 ft indicated). alarm on P808 and/or P601. g 2.6 Suppression pool water level 2.6 SUPPRESSION POOL LEVEL LOW below 19.5 ft ( .5 ft indicated), alarm on P808. g g

1 I

I I

I

< l l

l

I I

I I .

I i .

I I .

I I ..

1 I ~.-

I l

I I I

I I

I .

I I I I I

I I

I l

l I

I l

I _

l 1 ll 1 REV - 1 l

PAGE 3 0F 26 l

N/A l N/A ll E0P-0002 l l l l

l l ll l l l L. _

y l [NME 1] l l .

l l

. Suppression pool temperature can be 'l l monitored on the following instruments I l

in the Main Control Room. ;I l

I l .

INSTRUMENT NUMBER PANEL TYPE / RANGE I l

I I

I ICMS-TR40A,B,C,D P808 Wide Range /0 - 200'F l l

l l

l CAttrION #1 I l

I I

l If continuous LPCI operation is required to l l assure adequate core cooling, do not divert l all RHR pumps from LPCI mode. Leave at !

l I

.I least one RHR pump in the LPCI mode.

I I

I l CAtTTION #2 I

I I

l Observe NPSH requirements for pumps I

I taking suction from the suppression pool. (NPSH limit curves (LATER).

_ _ _ _ ~ . _ _ _ _ . . ~ _ - ~ . _ . _

g l I

CAtTTION #3 I

I .

I C,ooldown rates above 100*F/hr may be required to accomplish this step. g CAtTTION #4 Do not depressurize the RPV below 50 Psig unless motor driven pumps sufficient to g g

maintain RPV water level are running and g g-available for injection. g i

e l l I I I I .

I I I l . l l . I l r I I I I I I I l . I I I l I I I I I l l l l l l E0P 0002 REV - 1 l PAGE 4 0F 26 l N/A N/A l l 1 II ._.I I I L

s-l 3.0 OPERAWR ACTIONS I 1 -

l 1 Irrespective of the entry conditions,' execute the following 'l l concurrently: l I ;I l MONITOR AND CON'rROL SUPPRESSION POOL 'IIMPERAWRE (proceed to l I

l Section 3.1)'.

I I l MONITOR AND CONTROL DRYWELL TEMPERAWRE (proceed to Section i I

I 3.2). I I

I MONITOR AND CONTROL CONTAINMENT TEMPERATURE (proceed to Section l I

l 3.3). I I

I MONITOR AND CONTROL PRIMARY CONTAINMENT PRESSURE (proceed to l Section 3.4).

I MONITOR AND CONTROL SUPPRESSION POOL WATER LEVEL (proceed to I Section 3.5).

INSTRUCTIONS l CONTINGENCY ACTIONS 3.1 MONITOR AND CONTROL SUPPRESSION POOL TEMPERATURE [ NOTE 1]

_,,_3.1.1 Closo all stuck open relief C3,1.1 lE any SORV cannot be closed valves (SORV). within approxin.ately ;

l l

((2 minutes)) from first g g

attempting to close g THEN scram the reactor.

l *******************************************;..:.;.;;.;.;..:..:.************************* l g

SEE CAUTION #1 g l :. :. :. ; :. ;. :. :. ; :. ;. ; :. :. :. ****** ********************* .: :. :. :. :, :. :. :. :. :. :. : ********* ***************

l l l

,__3.1.2 Operate available suppression g l

pool cooling when pool temper- l ature exceeds 95'F.

l l l l l-3.1.3 IF suppression pool tempeg- l l

sture reaches 110*F l THEN scram.the reactor. g l

l SEE CAtTTIONS #2, #3 AND #4 l **:, :. :. :, :. ; ;. :. ; :. ; .: :. ;. :. :. ; :. :. ****:. ; ; :. ; :. ;. ;. ; ; :. ;*******************+++********************** l l

I . I I e l I I d, . I I l I : l l l l l l l l l 1 . I I I I I I I II i l l l N/A l N/A ll E0P-0002 l REV - 1 l PAGE 5 0F 26 l 1 I ll l l l

a- _. A L -- I FIGURE A l- '

! i i I!: '

l 1! l ! I il !' . !7

I

[} ! ,[ l I !'.l-}-istAT C= CITY TBrEMTAE UNIT -

I l l '

unceang@ ,aps '

'f !"- '

l l h 3 Il l i

,! l i I ! l l l l l l l l l' ta.

i , . l l l.

l ,, ,

u! ' i l l

'i .,,

l . .

"" ' l l o....,, l l i ,, , Il !

y[=

i I

h -

4 ,.,

I ! Il j ;

I g. . I ;t l I I, I

I i. I g ,

g I l l Mcznket.: tous am .

I l j , I l

l I see i

I I

l m i

I I

i l

l * '

l I

I '

I g

ise, ll l i l,,,,,,,,,............... I y

l i

,,......... . . , , , , ..., ......, .... . . , ,, ......, .. : , l i l ; , , , , ; ,.,,,,.,,,

l l

l i. .1 au- - l l e ae >m 4 m ee. = m um '

ien im =

I =w.w ..

i l

l l [ NOTE 1]

l l

1 l The main condenser (if available) should be used l l to divert energy from the suppression pool to the maximum extent possible. l l

l l

I l

i I

I I

i 1

I I

i 1 -

l I.

I l-

- I 1

I I

' I I

l I

I I I ll l l l l N/A l N/A ll E0P-0002 l REV - 1 l PAGE 6 0F 26 l l l ll l l l

y 3

8 l l ,

l INS 11tUCTIONS I CONTINGENCY ACTIONS l I

l ll 'I i

-l 3.1.4 E suppression pool temper- 'l C3.1.4 E suppression pool temperature l sture cannot be maintained l AND RPV pressure cannot be ;I I

I in the acceptable zone of Heat I maintained in the acceptable I l Capacity Temperature Limit in I zone of the Heat Capacity I I Figure A I Temperature Limit in Figure A I l

I THEN maintain RPV pressure THEN EMERGENCY RPV DEPRESSUR-l below the limit [ NOTE 1]. IZATION IS REQUIRED. Proceed to I E0P-0001; Instructions 3.0 and !

l Proceed to E0P-0001; I execute concurrently with this l l Instructions 3.0 l I

l M execute concurrently with I procedure.

this procedure. I I

I I

i 1

11 I

I I

I -

l I

I l .

l I

I l

l l

l l

l I

I I

l l

1 l

I I

, I I

I I

- 1 I

I I

l I .

I l

i .

I I e i

I I

l I

I l

I I I l I

l I I 1

l-I I

I I

N/A N/A E0P-0002 REV - 1 l PAGE 7 0F 26 l l ll l l l m

E i

~

CAITTION #5 l l

l I

l l While using Hydrogen Mixing System for drywell '+ l

)

I temperature control, closely monitor containment i g I pressure and temperature. ;l .

I I I i l TABLE A I l l l l LEVEL INSTRUMENT l LOWER TAP l 1TEMP ELEME!C/. INDICATED; l

l LEVEL ' TYPE RANGE NUMBER ELEVATION l l* TEMPERA 11JRE l I I ** . l B21-R605 (LATER) in i (LATER) (LATER) l Shutdown 0 in. to 400 in. l I l l I

(LATER) (LATER) l Wide Range -160 in, to +60 in. C33-R608 l(LATER) in I ** lB21-R604 l(LATER) in ; I I

I l l I Narrow Range 0 in to +60 in. C33-R608Al(LATER) in i (LATER) (LATER) l I C33-R608Bl

! 1 ll C33-R608Cl I ** C33-R608 l I

{

l l l

- C33-LR- l (LATER) (LATER) ' Upset Range (0 to 180 in.) l

. R608 l l

l (LATER) (LATER) IFuel Zone +50 in. to -150 in. 321-R615 (LATER) in

*** l l

l

Drywell area tempprature (M71); average the two points. I l

- 0 in, reference is 15 in above bottom of Steam Dryer Skirt; 162 in, above TAF

- - 0 in, reference.is TAF; 147 in, below bottom of Steam Dryer Skirt.

l l

I l

[ NOTE 2)

Drywell temperature can be monitored on the following instruments in the Main Control Room. g l

INSTRUMENT NUMBER ' PANEL TYPE / RANGE

' I 1 CMS-TR41A, B P808 Wide Range /0 - 200*F Wide Range /0 - 200*F l ,

1 CMS-T!43A,B,C.D.E.F P808 l I i If no'ne of these instruments are operable, then ;

l use oth,er sources of information as necessary. g l ,

. l l l l 1 l l ; l l l l . l 1 ,

l l

l 1 1 I l 1 I ll l REV - 1 l

PAGE 8 0F 26 l

l N/A l N/A ll E0P-0002 l l g l I ll l l l

o g o

t I

i I I

i l INSTRUCTIONS l COPTTINGENCY ACTIONS -

1, 1

g

. . ........................I......................., I l 3 i SEE CA(TTION #5 ;I '

y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ,; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ;,; ; ; . ; ; ; ; ; ; ; ; ; y, l l

l l 3.2 MONITOR AND CONTROL DRWELL TEMPERATURE [ NOTE 2]

I I

I l 3.2.1 IF the drywell temperature C3.2.1 E the drywell temperature l exceeds 145'F cannot be maintained below 180*F !

I THEN operate all available THEN proceed to E0P-0001; I drywell cooling to maintain l Instructions 3.0 g I drywell temperature less than ll AND I

I 180*F initiate a controlled l depressurization at approx-l 1. E there is no Primary imately 100*F/hr using turbine l

I System Boundary Leakage bypass valves or SRV's as l

I THEN operate drywell purge necessary. Execute E0P-0001 l

via Containment Ventilation concurrently with this procedure. l System or SGTS.

l I a. Assure it isolates if E the drywell temperature l radiation setpoints are cannot be maintained below 330*F l exceeded. THEN EMERGENCY RPV DEPRESSUR-l g

b. Shutdown purge to SGTS if IZATION IS REQUIRED. Proceed l temperature exceeds 212*F to E0P-0001; Instructions 3.0 l

AND execute concurrently with l l _this procedure.

2. E high drywell pressure l l signal is scaled in l BtTT NO P'RIMARY COOLANT l l

g LEAKAGE IS PRESENT. l THEN start the Hydrogen l l

g Mixing System (one train) to l

maintain drjwell temperaturel l 1ess than 180*F (operate l l

bypass switch as necessary) l l

l l l

3.2.2 E the temperature near the l Cold Reference Leg vertical l l

runs: .

l l

l l l

1. Exceeds the limits listed in l l

the temp'erature column of l l

Table A l l

AND the in'dicated RPV water l l

1evel decreases to that l given in the indicated level l l

column .

l l

l THEN disregard the l

, instrument for further l reliability l l

l l

'l l I I I I I I I I ll l l l l N/A l N/A ll E0P-0002 l REV - 1 l PAGE 9 0F 26 l l l ll l l l

- - - - . - - - - . - - - - . _ . - . . _ - - - - . . - . . _ _ . _ . _ _ _ ~ _ _ _ _ - - - . _ - _ -

7 s

i

. CALTION n6 d

i If the dr ell temperature reaches the RPV saturation temperature i

I (see Figure B) the RPV level instruments should be considered i <

! I unreliable since their reference legs have probably flashed. If IO' I this occurs, the. level indication will probably " peg high" even I '

I I though the actual RPV level may be low and decreasing. I I I l ,

I I i l rrctmE a I l l

! I I l l 1

I i l

l [$3E T$bN}%ki ,. : 3, ... a,.

WEdEIdI : wt , ~.

D%ie . . .m I

I I ,(. .

, +"s -

At. l ,

l 1 ,o; e. .

e m . .. - 4: ; 1

) I 1 y: M ';'_. .

l I

l

) .. n sm ..

l l

l "' ~

l .'

l .. .

, . [

j

I l

}.

e I

I I

J 4 NT~I*h I .,

n l l i t -

, g .l l

-l

I lt I

I

] t , .

l l

i l I! .,'I I

l i E .

,. I i

I l

l. _ _ _ _

_ n 5:e

. o.. i, l l 1 I l

l l l l l t i.,,..,.,~.,. - - -

-l l I' l

. . 1.

l

'~

.l. I i l l r i I i

l l r i l i

l l :

1 I i l l ll E0P 0002 l

REV - 1 l

PAGE 10 0F 26 l !

l N/A l N/A ll l l l l 1 I ll l 1 l !

-. , . . - - . , - - - _ . , _ . , s _m m

.. g I

l I ! $

l INSTRUCTIONS CONTINGENCY ACTIONS l I

,g '

......... ................................................ ]

l '

l SEE CAUTION #6 l --- ------- --

- - - - . :. :. :. : :. :. :. I ll I I l 3.2.2 (Continued) l l

l 1 2. Reaches the RPV saturation l l l limit as determined from l l Figure B (unacceptable zone) l l THEN RPV FLOODING IS l l l REQUIRED. I l l 1

l l a. Assure the reactor is [

l scrammed l I l I b. Open two SRV's I l

1 I c. Proceed to E0P-0001, l

l Step 3.0. Execute con- '

l l currently with E0P-0002.

I l I I I l I -

I I l I I

' I I

l I

i I I I I I I I '

I i

I '

l l -

I l I - I I , I I I I I I I l .

I I I I I I I

'I I l

l l l

! N/A I

N/A ll E0P 0002 l

REV - 1 1

l l ll l l PAGE 11 0F 26 l l l l l -- l l l

NJ l TABLE B I p

-l 4-l I

l LTEMP ELEMENT / INDICATED LEVEL INSTRUMENT LOWER TAP LEVEL !

l l* TEMPERATURE TYPE RANGE NUMBER ELEVATION :

l . l l

I l (LNITR) (LATER) 1 Shutdown 0 in, to 400 in. ***lB21-R605 I(LATER) inl I

l (LATER)

I l 1 (LATER) l Wide Range -160 in, to +60 in.lC33-R608 l(LATER) inl l

l g

I

- - lB21-R604 I(LATER) in] l l

l 1 I i

I (LATER) (LATER) Narrow Range 0 in. to +60 in. lC33-R608Al(LATER) inl I l l lC33-R608BI I l

I l lC33-R608Cl l l

l l ***lC33-R608 l l l l l l l l l l (LATER) IFuel Zone +50 in, to -150 in. lB21-R615 l(LATER) ini (LATER) l l

g l l ****lB21-R610 l(LATER) inl l

Use containment cooler inlet air temperature.

l l

- For those instruments there is no elevated containment temperature which will l l

cause onscale reading if the actual level is at or below the lower instrument l l tap, i.e; if the instrument reads on scale, actual RPV water level is at or l l

l above the lower instrument tap. l l

- - 0" reference is 15 in, above bottom of Steam Dryer Skirt; 162 in. above TAF. l l

- - - 0" reference is..TAF; 147 in. below bottom of Steam Dryer Skirt. l l l l l CALTTION #7 l l

If the containment temperature reaches the RPV saturation l

temperature,,the RPV level instruments should be considered l l

unreliable since their reference legs have probably flashed. l l

If this occurs, the level indication will probably " peg l l

high" even though actual RPV level may be low and decreasing. l l l l l l [ NOTE 3] l l < l l

Containment temperature can be monitored on the l l

following instruments in the Main Control Room. l l l l INSTRUMENT NUMBER PANEL TYPE / RANGE l l l l 1 CMS-TRY42A f

.B P808 Wide Range /0 - 200*F l l ICMS-TRX42A. B P808 Wide Range /0 - 200*F l l I I I l l l ; I I I I I l I I I l- 1 I I I I I I ll l l l l N/A l N/A ll E0P 0002 l REV - 1 l PAGE 12 Or 26 l l l ll l l l

1 I

I '

CONTINGENCY ACTIONS I l INSTRUCTIONS I .

I I

l 3.3 MONITOR AND CONTROL CONTAINMENT TEMPERATURE [ NOTE 3]

I : l I

l 3.3.1 IF containment temperature

~ I l Eceeds 90*F' I l THEN operate all available I I containment cooling and continue in this procedure.

I 3.3.2 IF the temperature near the C3.3.2 E the temperature does not I cold reference leg vertical l exceed Table B I

I runs exceeds the limits listed l THEN continue at Step 3.3.3.

I in the temp column of Table B

! AND the indicated water level I de' creases to that given in the I indicated level column THEN disregard the instrument for further reliability and l g

. continue in this procedure, g l

_ 3.3.3 E containment temperature l

reaches ((180*F)) and if g containment-pressure is below i l

l 2 Psid , l l THEN initiate containment purge l l '

via SGTS and continue in this l l

procedure., l l

l l

l

_ 3.3.4 E containment temperature can l not be maintained below 185'F l l

l THEN EHERGENCY RPV DEPRESSUR- l l

IZATION IS REQUIRED. Proceed l l

to E0P-0001; Instructions 3.0. g l

l A)ND execute concurrently with l l

this procedure. l

- - - - em....;,;,;,t.;;,;,*********************************************

g , l SEE CAUTION #7 l l *******; ;, a :. ; :, ;. , ;. :. ;, ;, ; :, . :. ;. ;, ; ;. ;. ;, ; ; :. ;, ;, ; :. ,, :, ********** :. ; . ;, ,, , . ,, ,, ;. ;. ;, ;, *********** l l

l 3.3.5 E containment temperature l reaches the RPV saturation temp l l

(see Figur's B, Page 10) l l

THEN RPV FLOODING IS REQUIRED. l l '

. l l l

l _ 1. Assure the reactor is l scrammed l l

l l

l

_ 2. Open twp SRV's l l

1 l _ 3. Proceed to E0P 0001, Step l l

3.0. Execute concurrently l l

with E0P-0002. l I

l I

I Il l

I ll l REV - 1 l

PAGE 13 0F 26 1: N/A l N/A ll E0P-0002 l l l l l ll l l 1

f l- [ NOTE 4) l I I l Primary cor.tainment pressure can be monitored on 'l ,

I the following instruments in the Main Control Room. l I : l l INS 11tUMENT NUtfBER PANEL TYPE RANGE I I I l ICMS-PR2A, B P808 Wide Range /0 - 75 Psia l l I I I I- CAtTTION #8 I I I I Observe NPSH requirements for pumps taking suction from I the suppression pool. (NPSH limit curves (LATER).

l l CAtTTION #9 I Elevated containment pressure may trip the !

RCIC turbine on high exhaust pressure.

l l CAtTTION #10 Bypassing Secondary Containment HVAC Isolation a y

signals may be required to perforu these steps e g

g- (inst' ructions (LATIR). g i I

, I l

I I I I I I I I I I I I I I I I l < l l I l 1 I '

I I , I I I l . I I f l l l l l 1 1 l . I I I I I I I I I I I I I I I 1 I Il E0P 0002 l

REV - 1 I

PAGE 14 0F 26 I

l l N/A l N/A ll l l I I ll l l

l l l l' INSTRUCTION 5 ColfrINGENCY ACTIONS I

=l 1 I

l' ' 3.4 NONI'!OR AND ColfrROL PRIMARY C0ffrAINMENT PRESSURE [ NOTE 4]

l l t, 1 3.4.1 IF containment and drywell l C3.4.1 E containment ventilation g j l temperatures are below 212*F l system isolates g l

l. THEN operate Containment l AND there is no primary coolant Ventilation System and Drywell l boundary leakage Purge via [1 CPM-MOV2A(B) and l THEN reset the isolation at P680 ;

4A(B)] to maintain drywell to I and restore Containment l

g

' containment differential l Ventilation System to normal l

pressure below 2 Psid and I before drywell pressure reaches l l g

containment to annulus 1 2 Psig, g differential pressure below l g 2 Psig. l l- c.:.;.********************************************* l -

l SEE CAUTIONS #8, #9 AND #10 l l

g. l I I l t l 3.4.2 H containment to annulus l l differential pressure reaches l l l

l 5.0 Psid l l ,'

,l THEN EMERGENCY RPV DEPRESSUR- l

'l IZATION IS REQUIRED. Proceed I l

to E0P-0001; Instructions 3.0 l

_ *l l l l

AND execute concurrently with l l i

this procedure. l

-l l !

l , I l l

_ _3.4.3 E containment pressure reachesl C3.4.3 E containment cooling is not l~

((7.5)) Psig 1 effective in maintaining l l

l THEN operate all available containment pressure less than l 6

containment cooling to main- ((9.0)) Psig l l

l tain less than ((9.0)) Psig. THEN attempt to restart drywell l l

cooling. l l l l l l e l l I l 1 I I l I I 1 I . I i '

. I l' I

. i-l l . I ,.

I I I I I I .

I I I

l~

l I' I i 11 1 I I I N/A l N/A ll E0P 0002 I REV - 1 1 PAGE 15 0F 26 l 1 I ll l l 1

'< l cat.TTON #111 I ,

I If continuous LPCI operation of A and B RHR pumps is i 3 '

I required to assure adequate core cooling then do not .

I divert A or. B RHR pumps from the LPCI mode. l I l I

1 FIGURE C l I I l . I I l .

I su I i I I I i u i maus commeer monas tant I I u

I I I i

-I- 1 l

l l l l l w l l I 1 '

I I .

unace m ans sem . l l n. I i

I ~ ' '~; '

F. l#

l l

s _t-- 2 __.. -

-a u.t ,

I l .

2 l

= i. .:. l 1 4..:. .

__ . - l l = -.

. I ;F sg:.-. accmasu sous u: -: l l -; -,-z I I ..

_ I

.u- -

l n .

l 1

.._ ... r:=.= =,

,. l 1 ~~

' . .=. u ..a.. , l l n = > - , .; : - - l

=- r : rs a i l

, - == .Z - :. .i h ":1 l l -

=. .ai .+.: ..r -

l l

,l .: ::

l ge I * -*: I r. , -

.. . , , . , , . ' ~

-l

~

j= .#. = :: i... .

l I- a w a = r. . s. l

- "I

- =w I l .. I I . .

I I -

. . . I I I I I I l i I II I I I I N/A l w/a ll sor-coon I av-1 l n m is or as l l l ll l l _l

. e

^

l l l

l INS 11tUCTIONS CONTINGENCY ACTIONS I l

I l l

l

.. ... . ....................................................................... l 1 SEE CAIRION #11 II f' l .. ........................................................

................. , l

~

l l l

3.4.4 IF containment pressure reaches l C3.4.4 E containment pressure cannot g

((9.0)) Psig be maintained below ((12)) Psig l g

AND adequate core cooling is THEN initiate suppression pool l g

assured cooling even if adequate core l

g THEN initiate suppression pool l cooling is not assured.

l cooling to maintain less than l l l

g

((12)) Psig. l l l l l

l 3.4.5 g containment to annulus l l differential pressure cannot be l l l

l maintained below 15 Psid or l drywell below 25 Psid l l l

THEN RPV FLOODING IS REQUIRED. l l l

1. Assure the reactor is l l

scrammed l l l

l l ' l l

2. Open two"SRV's l , l l . I I l

3. Proceed to E0P-0001; Step l l l

3.0. Execute concurrently l l

with E0Pr0002. l l l l l 3.4.6 E containment pressure exceeds H C3.4.6 E Hydrogen Purge to Annulus is l l

acceptable zone of Figure C ll not effective in reducing l l

THEN vent the containment to i containment pressure within l reduce pressure below Figure C; acceptable zone of Figure C l l l OPEN Hydrogen Purge outlet to THEN perform the following: l l Annulus [1CPP-MOV104 and 105] l l on [1CPP-PNL102] (Aux Blds EL l __ Bypass the Containment l Ventilation (details (LATER) l 170 feet). e l l 1 l

Open CT}E purge valves (P863) l l [1HVR-AOD127, 128 and 166] to l l ,

vent containment to the l l

Ventilation System Exhaust. l l . I I e l I I I I I I l . l l 1 1 I I I I I I- 1 I I I I l l ll l l l l N/A l N/A ll E0P-0002 I REV - 1 l PAGE 17 0F 26 l l l ll l l 1

~

l [ NOTE 5) l l Suppression pool water level can be I I monitored on the following instruments !m I in the Main Control Room.

l . l .

l , INSTRUMENT NUMBER PANEL I TYPE / RANGE f l ICMS-TR40A,B,C,D P808 Vide Range /-18 to +4 ft* I ICMS-LI23A, B P808 Wide Range /-18 to +4 ft*

0 ft indicated is 20.0 ft of water level in suppression pool l l CAUTION #12 Observe NPSH requirements for pumps g taking suction frem the suppression g g

pool. (NPSH limit curves (LATER). l l l FIGURE D l

l - - ..,

l j-l

.. ~

l 1

..E'ccc*uaaa: u a u a u u.s a u p e ,

a l

l l ;

i , . I I I I i i !! O ' -

jill iis' ! i I l l 1 L l! l i l !

i l l

l l l! i l I l i l

l q ,

l ll ' f i l 1 i

i I

l lI p

, i i

j l l

.I i I I l l 1 a = l l g I l $

l ll l

.I I I i 5 l

3 I l

l l !! !

'l I l l

[. lll! i' . 3 l

.l. . 9 ,

r i

! l .

! 1 s l

'l a.; il i l l I

. z i i l

-l ? ! I !! . : I . l l l 1 I !'i l li l I ,

I

.. E ni % .i un r ;p .

j i .. ...

. i i i ,, ,; , g ; ,

i l l l ll l l l l l N/A l N/A ll E0F-0002 l REV - 1 l NGE 18 0F 24 l l

l l ll l 1 l

l:

I 1

C0ffTINGENCY ACTIONS I l INSTRUCTIONS ,

I 'I l

I l 3.5 MON 11VR Alt CONTROL SUPPRESSION POOL WATER LEVEL [ NOTE 5]

l .l l =u_u;.__uumn_w_.=umu=uu= = = =;.muuuu;.=;..;.uun' I I I SEE CAUTION #12 l

............. . ...................................................... l 1 l l

I 3.5.1 Maintain suppression pool water l C3.5.1 E suppression pool level level less than 20.0 ft (0 ft l increases to 20.0 ft (0 ft I indicated) and greater than l indicated) 19.5 ft ( .5 ft indicated). l 0,,R if CST level decreases to l g

l 2 ft 4 5/8 in. l

1. IF there is any potential l THEN confirm auto transfer or j l

g

-for abnormally high activity l manually transfer HPCS and RCIC l

g levels in the suppression l suction from the CST to the j g

pool I suppression pool. l g

'DIEN request a sample l l analysis by Radio-chemistry l 1. HPCS E22-MOV105 opens and l l

g Personnel, then E22-MOVF001 closes l l l l

2. Use all available normal 2. RCIC E51-MOVF031 opens and l g makeup if suppression pool then E51-MOVF010 closes l l

1evel is-low. l l ,

E suppression pool level can

l l

not be maintained below 20.0 ft l l

j @ adequate core cooling is l

, l assured l l

j. l THEN terminate injection into l l

l the RPV from sources external to l l

l the primary containment. l l l @ proceed to E0P-0001, l l l Instructions 3.0. Execute l l l -concurrently with this procedure l 1 l I

[ ___3.5.2 E suppression pool water levell l l cannot be maintained in the l l l

acceptable zone of Heat l l

Capacity Level Limit (Figure D)! ,

l

_l THEN EMERGENCY RPV DEPRESSUR- l l IZATION IS'. REQUIRED. Proceed l l l -to E0P-0001; Instructions 3.0 l l l @ execute'these concurrently l l l l with this procedure. l l l l l l l 1 I I l l l 1, l 1

1. I I I

! I I I I I ll l l l

~l N/A l N/A ll E0P-0002 l REV - 1 l PAGE 19 0F 26 l l l- -l ll l l I U

i CALTION #113 ;

l r i _ i l Cooldown rates above 100*F/hr may '

l be required to accomplish this step. I I .

I I

I CALTION #14 3 I I i I

I Do not depressurize the RPV below 50 Psig I unless motor driven pumps sufficient to l I

I maintain RPV water level are running and .

available for injection.

I I I piccgg g 1 l l 1 I

Suppression Pool Load Limit l l l .

g

, I l l l' I !

l .l . , 'lll l *ll' !l!! !!!! !!il I !' l!!i !!!.' i!I! !!!i !!I IIi! illi ll!! ! l il i 11!: !T i: %' .

j.

j[j i!!i !. E,i-2 I -., ll i i i Ij ! i ::- :.! I i - !'I ,;

'l l.

, t, t .ll

, T i

.t i.i.!

Ts:. J,!j

.il .!

54fP9tES$1GI PtR LOAS L18tli r!l

's ;

i g , ,. + y i

' ' l iI: ii 4i

'!! ill iii! 'j !iii i:i li .J I ... ~

i f IF!iii IIli IIii}iili !fiill!l 'il liiili i j , . , !!!. i .l!' i I ( l ij i ; .. i 'i i 11i 'mitj i i ii . ! l I l1: i I

.3 I 1

i I ! I i

l

! li

! iI .

ll ..I

!!l .'s

'i,!

I ,

i e I ii! I l

I j.. i i L. .ig;Ii ;

i; i l' i I i:i, in l;;i-

.:: il I 1

i.i !!'!', '.,!l i::: u l ; ep m r, i I

.i i; , i i , :,:i l ,

3 ,, ' '

l l 2 , .

'l I . ! i !!!! 'i l lit-i

! le l' i i

' i i ,.

l l l j ,, l

! j!!! I' f ,, Tj :n'rswun sbu "

o, l

l

i .

l l l j -2 l ' '

l I I I

l i

-3

. l l

l '

I I -* I l

-s I I ll l 1 . ' l l'}l--

I -s

I l

l l ' l l l_ , ..s , T 9'

- .l.

g. - t. :., , ,

[ ,

lN a. s c,. o

,ooo ,a l l l = e i

. l l l l l l l l 1 l l l l l l 1 1I I I I I N/A l N/A ll E0P-0002 l REV - 1 l PAGE 20 0F 26 l 1 I il l l l

en e

i I I I INSTRUCTIONS l CONTINGENCY ACTIONS l ?

I l l -

l

................................................................................. l I SEE CAlTTIONS #13 AND #14 ;I l ................................................................................. l l l l

l l 3.5.3 E suppression pool water levell C3.5.3 E suppression pool water level I cannot be maintained in the l AND RPV pressure cannot be I l acceptable zone of suppression l restored and maintained in the I pool load limit (Figure E) l acceptable zone of the I THEN maintain RPV pressure j suppression pool load limit I g 1 below the limit l THEN EMERGENCY RPV DEPRESSUR-l IZATION IS REQUIRED. Proceed to I E0P-0001; Instructions 3.0 I l

g l AND execute these concurrently !

g l with this procedure.

l 3.5.4 WHEN primary containment water l l

1evel reaches 158 feet Mean Seal I l

Level (MSL) l THEN terminate injection into l l

l the RPV from sources external l g to the containment regardless l g l '

l of whether adequate core l

' g cooling is required l ;

l l l NOTE l g l

, I l I

l This corresponds to a static system l g l

pressure on RHR pumps of approxi- l g l

mately 25 Psig above containment I g' l pressure. l g I I l

"END OF E0P-0002" g i l I i 1 , l 1 1 I l i I I I i 1 I . I I '

I l I I I I I I i 1 I I I I I I I I I I I

'i i l l ll l l l l N/A 1 N/A ll E0P-0002 l REV - 1 l PAGE 21 0F 26 l l l ll l l l

(

ENCI/GURE ^ 1 FC: L [:E FIGURE A: HEAT CAPACITY TE"FERA!LRE '!";T C;RVE l I

.\

egpeemska78d W e M M M - - l l l

! S . I I I I 3 3 I l I 'l '

e n== = em sus num u== e== i=m :== = = r-r- ==s = = = = == m:=r j i, . .

I j

}

w m -

i :

i . : _

,** l l M : - ... , i i o- e : ; . .

- " ~ '

l : _- i i : : : .

j w -

-g: . . _ _ .

g- - .

l l . -

j I : ; - 1 I i l

g'

.:5 .=: . I

-4.

. = E .. ..._,. : I ;

I : _ .

. .. , l

=

g- = ; --l ::

g- - .._ l l.

,_3. .. .

l Ig i ,--g- - . . . ,

._ ,l I _ . . - -

--: l 1 e ; .. .; .. . . . .. .= l 1 3 _

4 .

.:g l I, -

E

= -

= --

l

l. =

-g: --- [

Ig g

_. .M:t = . . . ._

l

l. Q _ . : == l l =;3

: - : := l 1 : l m ::

I l e

Q +. :: -- g l g i I -

"i E!

J

.=

[

l -

g 1-

,_ l

} . -

l l .

3 3C .< ,_

l l l

= --

.I -

- :: - :=.

l j '

l

. ' E - .- -- - 1 . _;. . (

..I : ;- .

r= l

_f y

.-.*~

': E y=> L

. 2. . l l - :: -

l l :: : ;;; .-

] $ --

- I

-- - 1,

_. I, j g ENCI43URE - 1 PAGE 1 OF 1 ll E0P-0002 REV - 1 PAGE 22 0F 26 11

~ :. y. g ?. , ::t : RE 2. m <\T kr ' E'?E?:: - -

Tampersom (*F) near cold saferesse Los Isotruesst vertical numa w o e = w ,

. .. 1 o .,3s ; 7 -)

_mmm my - s-nve=r -M net

--;W 4,Mggsi.Al ,ms g __+ ; M ~ W A M. E % W 5'; #pi!

=

~ p--.3 e,. , =;- g -- . ?-.-rg-*?@ rggg

( a*

- . = = = c

-g ""+-M -ee _ . n- . .,;

. :- r T3 - * ~ ^ ~ - -

g r 12.gp'_.

gg_.= - gepaggg' g" 3 -* p grn g gg. pigg.; -.

1 w g g= y = 3. ;3 g-

, y + g-= -

1

'^

3 45 g%y% 3

.q q.

_.A;

. -=

l g-~

G

_9 gqq : -

wwy

-~+=. iiE 3 , ;-aili 4 3 - 5 @ f. ~~: E.sg#

-z =_ g = g* ~ qaig.g =!

.u* s g_p w4 c i ._ I _ _' .M %s .b . i ' ' .f . W 8 't Eifas'_ = -- -

l = ' Auli ga_ :

'~

M. 9%$Df-N r i "W.% .U *4- E.e3 fr i. acail

,4 . siilig . ; T

rT ; F@!!ge.gNgrig.;

r '

a s =*. ; s g W . s.ggg i W d- =.

a s--... _'_sf [ -- = m

=.. -m MEN =Q

-:g = = = Ww ;=@+3_ 5* e*e 2

M'bA i

\

m. .:n-a. w- -

l l .El B iilsiii 4 E EIE*if5~ - 4 M lii3EiEi? M.F'3.'=5 4 9 h c= -4M l i

i

M ~$

4 28#i!!!?#8'43 d'M % ~ "Tisis*dA b h .ar.=4

4 ?t Mh=gmW. ?% 4** "E-*7+/W

.=$. .

l y5 $ l... $ Q: r%5e' . ~ ^ - A ; ;~'~.= 2t * = . ' % MT : ' ' ~ ~ ' ~

I

, e ,

l l

l lg 1

l lY I

I *E I f l

I l

8 3 $-

~

I -

I i

g

. - l I

8 i

t I

l B I

!I I !

l l I

l l

i t

- I I - ----

I I ENCLOSURE - 2 l PAGE 1 0F 1 ll E0P-0002 l REV - 1 l PAGE 23 0F 26 l l l ll l l l

0 F-r-

! 120 - -

l Mt! MARY CONTAllfDT PRESSURI LIMIT e _

i .

! ut '. .

1 g _,

i 100, - -

i .

,7 90, _ ._, .

=

I _

4 _

._.4. .

' i -

80 3 . _ . ._. _.__

~~UNACCEPTABI.E ZONE

.. . , . .g . _..

I,70..p.

...4... .. ..... .

g._ _

=.. . l

_ 4 _._ ..

4.._ .__;

l f

.- . _. p _

. . .g.

_ .j.= .

, l

. w . . ._. .... . . ,

.. -_ g I

. .; _.._ _.. _ 2-. >. . - -

4 ...!_. . _ .. . . . _ .. -

1

,_ l 60 . _ _ _ , . _ , ...

,...__. _....- - - = .. . l

. . _,... .9. - . _

[ . . .

. j .. .. . . _ . . _ . .

-4_._

- .. = . u.

l

..-.4 ACCEPTABLE ZONE....

i o,,,

a 50 -3

..._ ,_.._- - 4= - . . -

l w

., . . " . _- ~'_ - " . " , . -__~. "- ,~-

. _... l i.

_ -t.

. - - [

,_ .._- l

._ .. . +.. ... p .. . _ . _.

40 -

_. 3 . _. .. . . ,

- _ ... _ l

_ . . ._t- _ _

,_....._.-t_._..

.. l 4__. .

3.. , _ _ u_ ...,.... .

l 30 .. .w

_ ..C._

. . _.4 ._!....

.4..... .

l

_ . . . . . . t _. .

.. . ...- . - ..... I

__ a. .y_. .. . . . i g._ . - .. _ . .. __ . . .

. .. . . . . .=. 4 .

..l... . _ . _

t

__.. ._ ... . . . . , _ .. .. . . . l

_.___ _....._ . .. .. .. . _ . . . .. . l

.. . _ _ _ l 10 " '-

'--- -- --"--- u

_.._ . .. l 0 . . __.. ...._ .

l 0 10 20 30 40 50 60 70 SO 90 100 I

, ~ .- l I I II i I ENCIDSURE - 3 l PAGE 1 0F 1 ll E0P-0002 l REV - 1 PAGE 24 0F 26 l I ll l 1

Isc;cs m a FtLL st:E F:r.hE N ' -

7 g -

27 IEAT CAPACITY LEVEL LDl!T 26 .

23 ,

24 ._

t as __

22 ._-

ACCEPTABLE~'

ZONE '

21 ._

w .

w

= 20 -

.---- I 19

- := . . . - -

is

+ --- -- -=

= -.

- I

, --. _ . ._ __%._. w_ . _._ .

'N- l 16

- ~_~~--

.- 1_ _

l 15 _- ._ I

= 14 .

I

l. ! 13 -

l u_ ._. -_ _ . : UNACCEPTABLE ZONE

~

~. ~

l I i

,_ __ . . . . ... ,_.. .. l ,

- - ~- ; .

11

- - - :- .. 7~ i 1a - . _.

1 l

9

_.. L ._, .

g _ . . .

y l

1 i

l l

. 4 l

j' -

U-M M_

l ~l 0 ,

- ~

l S to as I

i se e 15 zo I i l i 1 I ENCLOSURE - 4 PAGE 1 0F 1 l E0P-0002 REV - 1 PAGE 25 0F 26 l l ,

I l

l 1

i ENCLustJE - i a S EE '.L kE E; L "'E5A..N i:.

-s. . . . . - - --

3 .* Ind4cated Suppression Pool Water Level. (ft.) . , ,

- -- - * , + + + + + + + 4

. .. i i I I l t I l " " *

J i

e 4 e m + W M " 8 *

w a

. _. 4,_:

- -+

=.9._

2

_. ! 1 l

I _ -

l ._._. I 1 _. . ...._ ,

_1.., ..... _. ._. ._ . .

j __ , _ _ . .

l ..

i

_ f.

l --

. =: -

._ . =..

I l ._

. . . . _.__ l j .. ... . . . . . .. .

l

... . _ . . . . . . . . . . . a l

.. . . . . ... .. .g ..

g l - -

. . . - . .. . + ,

l 5 . . _ . . _ ,

. . . .....y._- .. ,... ,

j 4 . . _ .. .. .

j l

m .. .

l __, . . . _ .. . . . ._ . . :. .

. __. . g....9

, .... . 2.

- l e ..

._. s _. , _... . . . .

'1..

y .. g

.i - -

u

,,, _,,m,,.... . .

g l

j g _ _ . __. ;

g g .

- I 1

- us I .

S.

u'.

I l

I I- __. _. _

I ..

l

,e.

. . . . - . f"" e i

.. . . . . ]

.l --_.. . _e. . _ _ . .. _.

E .

.l.5.s.

4

, _ _ . , .... . ._ . m 6.. _

_i _ _. .-

____. . _ . .. i

. i, . _

i j

, i l ENCLOSURE - 5 PAGE-1 0F 1 E0P-0002 l REV - 1 PAGE 26 0F 26 l l 1 I

l i

l .

I -__ --. _ . -. - . -

I I

EMERGENCY PROCEDURE - SECONDARY CONTAINMENT CONTROL l

' l TABLE OF CONTENTS l l

SECTION PAGE NO. l 1

1.0 . PURPOSE 3 l l

2.0 ENTRY CONDITIONS 3 l 3.'O' OPERATOR ACTIONS 5 I

. TABLE I 6 l 1

TABLE II 10 l l'1 TABLE III 12

, l I.

n- -

1 I

I I

I

, I I

. I l

I I

~

l I

i i II l

. . N/ A . .l N/A -ll E0P-0003 REV - 1 PAGE.1 0F 15 l l 11 l l l

+

" " " ' - - - 4 4 _ , _

'~ . y o

_l THIS PAGE INITXTIONALLY LEFT BLANK l l

1 -

1 l

I I ; I l

I I

.I .

I I

I

..-1 I

I I

1 I

I I

.I 1

.1 I

I I

I 1

I-I I

I I

I 4

I I

I

'-1 I -

' I I -

1 I.

- I i.. . 1 1.

l I

l

.I l.

.I -I I

I

'l I I

.I i

l I

l-I l

l- ,

I-I 1

1 l' -

I I .

I I

I I . -f - .I l-I I

I I

.I l'

I I

. I l-I_

1

'l 1 i

l I

I i

I I

'l

~

N/A. N/A E0P-0003 .REV - 1 PAGE 2 0F 15 -

" ~

-1 I II I I I

-1 1

l l 1.0 PURPOSE l l

l l 1.1 To protect equipment in the secondary containment. 'I I

I I 1.2 To limit radioactivity release to the secondary containment. ;I l

I l

AND l

')

l -

) l l _ 1.3 Maintain secondary containment integrity. l I I l OR I I I l _ 1.4 Limit radioactivity release from the secondary containment. I I I l 2.0 ENTRY CONDITIONS I I I I _ 2.1 Any of the following secondary containment conditions: I I I I

I 2.1.1 Differential pressure at 0 in, of water or positive.

I I I Any area temperature above the maximum normal I 2.1.2 I operating temperature per Table I of page 6. I I I I

I 2.1.3 Any HVAC cooler differential temperature above the l ' !

- maximum normal operating differential temperature on Table I on page 6.

I 2.1:4 Any HVAC exhaust radiation above the maximum normal

, operating level per Table II on page 10.

I 2.1.5 Any area radiation level above the maximum normal

~

operating level per Table II on page 10.

2.1.6 A floor drain sump water level above the maximum normal operating water level per Table III on page g g

12. ;

g 2.1.7 An area watpr level above the maximum normal operating water level per Table III on page 12. g g

I I I . 1 I .

I I I l -

l l . I I I I I I I I I I i l I

l l l 1 l l l l l l i

l I N/A N/A E0P-0003 REV - 1 PAGE 3 0F 15 I I ll l l l t

I' i 1,

(NOPIE 1] l j

Secondary Containment Temperatures are monitored

-l l l ce the BOP computer (points (LATER). ,

I l Secondary, Containment Radiation levels are l l monitored in the Main Control Room as follows: l I I l- INSTRUMENT NUMBER PANEL TYPE / RANGE I l l l 1RMS-RIX5B P863 Effluent Recorder /(LATER) I 1 IRMS-RIYSB P863 Effluent Recorder /(LATER) I -

l 1RMS*RESA(B) DRMS Fuel Bldg' Vent Exhaust /(LATER)' - - !

l 1RMS*RE125, 126 DRMS Main Plant Exhaust Duct /(LATER) !

l 1RMS*RE110 DRMS Auxiliary Bldg Ventilation /(LATER) !

I 1RMS*RE11A(B) DRMS Reactor Bldg Annulus Vent /(LATER) !

I 1RMS-RE103 DRMS I SGTS Effluent /(LATER)

I Various DRMS Area Rad Monitors in Aux I

,I Bldg & Fuel Bldg /(LATER) l Secondary Containment water levels are monitored I in the Main Control Room as follows: ;

I INSTRUMENT AUMBER PANEL TYPE / RANGE

l .. I I

1DFR-LI134 P870 LPCS Rc,om/0 - 100%

I 1DFR-Li135 P870 A RHR Room /0 - 100%

! 1DFR-LI136

_- P870 RCIC Room /0 - 100%

.l IDFR-LIJ 37 P870 C RHR Room /0 - 100%

IDFR-LI138 l P870 B RHR Room /0 - 100% g i I l-

-l l- 1 1 I I I I I I I l l

-l

1 l I I -

l l= l ., I I I i- 1 -

I .

I i l l l 1.- .

1

~l I

l I

.I I

~

l I i l I

.I I I I i i 1 l 1 N/A N/A E0P-0003 REV - 1

'l ~ l l PAGE 4 0F 15 l

=l I ll l l l we-e -- -w-- --_mm ---a-- - - - - -

I l

3.0 OraxATOR ACTIONS I ,

Irrespective of the entry conditions, execute the following concurrently: f.

'l I ?

l .

I MONIER AND CONTROL SECONDARY CONTAINMENT TEMPERAWRES (proceed to Section; I ,

I 3.1) [ NOTE 1)., I I

I I MONITOR AND COVTROL SECONDARY CONTAINMENT RADIATION LEVELS (proceed to l l Section 3.2) [ NOTE 1]. I I I I MONITOR AND CONTROL SECONDARY CONTAINMENT WATER LEVELS (proceed to l I

I Section 3.3) [ NOTE 1).

I I l l l l l l l l l l 1 I I I I I I I I I I I

. l I

.I el l 1 I I I I I I I I I I I I I I I I I I I I I I I l I I l I I I I . I I I

~

I l I t I I I I I I I I 1 I I I I I I I I I I I I

-1 I N/A N/A E0P-0003 REV - 1 l PAGE 5 0F 15 l ll l I I ll l l l L.

e.

4 l TABLE I l I !

l

-1 Operating Values of Secondary Containment Temperature 'I }

l t l

SECONDARY l l II l l ALARM l MAXIMUM NORMAL l MAXIMUM SAFE I

.,l l C0ffrAINMENT LOCATION

- I I l l I' l HVAC COOLER DIFFEREP(TIAL TEMPERATURE l l

I 1 I i 1, I I I

I l MSL Pipe Tunnel (LATER) (LATER) (LATER) l I I I I

' I [ RHR Equipment Area 1 29'F (LATER) (LATER) l l l l

RHR Equipment Area 2 29'F (LATER) (LATER)

RCIC Equipment Area (LATER) (LATER) (LATER)

RWCU Heat Exchanger Room (LATER) (LATER) (LATER) l l RWCU Pump Room 1 (LATER) (LATER) (LATER) l RWCU Pump Room 2 (LATER) <(LATER) (LATER)

RWCU Valve Nest Room (LATER) (LATER) (LATER) l ,

RWCU Demin Room.1 (LATER) (LATER) l (LATER) i -

RWCU Demin Room 2 (LATER) l (LATER) (LATER)

< l i I 1 l l

g l RWCU Demin Valve Room (LATER) (LATER) (LATER) l l I I I l

g l RWCU Rec Tank l (LATER) l (LATER) l (LATER) l l l l I l

l AREA TEMPERAWRE l l

-l l l 1 1 I l l '

l MSL Pipe Tunnel g (LATER) (LATER) (LATER) l l l

! l l RHR Equipment Area 1 110*F (LATER) (LATER) l l

l l l l

g l RHR Equipment Area 2 117'F (LATER) (LATER) l 1 l I RCIC Equipment Area 185'F (LATER) (LATER) l l

1 i RWCU Meat Exchanzer-Room (LATER) (LATER) (LATER) l l l

t l l ~

RWCU Pump Room 1 - (LATER) (LATER) (LATER) l l

l *

'l RWCU Pump Room 2 (LATER) (LATER) (LATER) l l

1 1 I I I I I i

1. I I I I I I I I I 11 I I I l N/A l N/A ll E0P-0003 l REV - 1 l PAGE 6 0F 15 l-I -l ll l l l

.- - - - - _ . . - . . . _ - . -. - .__ _- . .- . - - _ . =

m; l INSTRUCTIONS l ColfrINGENCY ACTIONS l l

l :.

3.1 NONITOR AND CONTROL SECONDARY ColfTAINMENT TEMPERK111RE 'l ',

l I -

I ll l _ 3.1.1 Operate available area unit l coolers. .

I

l 1

-l ~

3.1.2 IF secondary containment HVAC l 1 i

l Ahaust radiation levels l I

l exceed (LATER) Cpm while perforal I I ing Step 3.1.5, 3.1.6 or 3.1.7 l I l THEN isolate or confirm isol- l I ation of secondary containment !

I !

l HVAC.

'l. l l

l 3.1.3 IF secondary containment HVAC l C3.1.3 E space temperature is above I exhaust radiation levels l 212*F l exceed (LATER) Cpm while l THEN stop SGTS.

I performing step 3.1.5, 3.1.6 l g I or 3.1.7

l g l AND l I [thespacebeingexhausted l

! is below 212'F l g I THEN initiate or confirm l initiation -of SGTS. l

[

I l

l g

_ 3.1.4 E secondary containment HVAC l C3.1.4 E bypassing high drywell l 3 g isolates while performing l pressure and low RPV water l step 3.1.5 ,3.1.6 or 3.1.7 l level secondary containment l AND l interlocks are required g g

g-H secondary containment HVAC l THEN bypass these per l exhaust radiation level is l contingency actions details l l g

below (LATER) Cpm l (LATER). l g

THEN restart secondary l l l g containment HVAC. l l l l l

g- 3.1.5 g secondary containment HVAC l 4 g exhaust radiation level is l below (LATER) Cpm l l

THEN operade available l l

secondary containmer.t HVAC. l l l

l l

-l l - _ 3.1.6 E any area temperature exceeds l l l

its maximum r}ormal operating l 4

l temperature per Table I l

j. THEN isolate.all systems that l l

are discharging into the area l l

except systems required to l l shutdown the reactor, assure l l

l adequate core cooling or l

! l suppress a. working fire. l I l l

I I I I I

! l I I I l l ll l 1 I l N/A l j N /A ll E0P-0003 l REV - 1 .l PAGE 7 0F 15 l l

1.__y ll l l 1

g 4

l TABLE I l l I l Operating Values of Secondary Containment Temperature *l l l l l SECONDARY l !l ,

I l CONTAINMENT LOCATION I ALARM MAXIMUM NORMAL MAXIMUM SAFE l l l l l l HVAC COOLER JIFFERENTIAL TEMPERATURE l 1 l l l l l l MSL Pipe Tunnel (LATER) (LATER) (LATER) l l l 1 I l

l l RHR Equipment Area 1 29'F (LATER) (LATER) l l l l 1 l

l l RHR Equipment Area 2 l 29'F (LATER) (LATER) l I I I I I l l l RCIC Equipment Area (LATER) (LATER) (LATER) l l l l 1 l

I l RWCU Heat Exchanger Room (LATER) (LATER) (LATER) I I , I l

! l RWCU Pump Room 1 l (LATER) (LATER) '

(LATER) I I I

! I RWCU Pump Room 2 (LATER) (LATER) (LATER) !

l l l

I l RWCU Valve Nest Room l (LATER)

(LATER) (LATER) ,I I .. 1 l

l RWCU Demin Roem.1 l (LATER) (LATER) (LATER) 'I I l l l RWCU Demin Room *2 l (LATER) (LATER) (LATER) l l g l l ,

l l

! I l RWCU Demin Valve Room (LATER) (LATER) (LATER) l I I I I I I l RWCU Rec Tank l (LATER) (LATER) l (LATER) l I I I I l AREA TEMPERATURE l I I I I I I MSL Pipe Tunnel (LATER) (LATER) (LATER)

RHR Equipment Area 1 IL7'F (LATER) (LATER) l RHR Equipment Area 2 117'F (LATER) (LATER) l RCIC Equipment rea 185*F (LATER) (LATER) l RWCU Heat Exchanner Room (LATER) (LATER) (LATER)

RWCU Pump Room 1 (LATER) (LATER) (LATER)

RWCU Pump Room 2 (LATER) (LATER) (LATER)

I I I I I I I I I 1 I I I .I I I N/A N/A E0P-0003 REV - 1 PAGE 8 0F 15 I I ll l l l

w I l l

INSTRUCTIONS CONTINGENCY ACTIONS I

, I

~l

'l 3.1.7 E a primary system is C3.1.7 E a primary system is l

l I discharging into an area , discharging into an area l THEN BEFORE any area temp l AND an area temperature exceeds l I reaches its maximum safe l its maximum safe operating l 4 l operating temperature (Table I)I temperature in more than one l l proceed to E0P-0001; l location I I Instructions 3.0 and execute THEN EMERGENCY RPV DEPRESSUR- 1 l

I concurrently with this l IZATION IS REQUIRED. Proceed to l I

I procedure. I E0P-0001; Instructions 3.0 l l @ execute concurrently with l I this procedure.

'l l i I I I I I

~l l I I I I I I I I l .

I I

I I I l l I I 1 I I I I I I I I I I I

~l I

, I I I I I l l l 1 l I I I .

I l l l

1 I .- l I I

.! . . I I I I 1 I I I I I I

-l l l l 1 I

.I I I I ll 1 REV - 1 1

PAGE 9 0F 15 I

l N/A l N/A ll E0P-0003 l l l l l ll l l l

l TABLE II 1 l l I Operating Values of Secondary Containment Radiation l I

l I SECONDARY -l l l l l l l CONTAINMENT LOCATION ALARM MAXIMUM NORMAL l l Effluent ' MAXIMUM SAFE l l

l l Recorder IIRMS-RIX5B1 l (LATER) Cpm (LATER) l l Effluent (LATER) l l l

l l l l Recorder IIRMS-RIY5BI (LATER) Cpm (LATER) (LATER) l I l Fuel Bldg Vent i l

I I l I

l Exhaust (1RMS-RESA(B)] (LATER) Cpm (LATER) 1 (LATER) !

l l

l Main Plant Exhaust i I l Duct IIRMS-RE125, 1261 l l (LATER) Cpm (LATER) !

I (LATER) l Auxiliary Bldg l l

l Ventilation (1RMS-RE1101 l (LATER) Cpm '

l

! (LATER) (LATER) l !

l Reactor Bldg Annulus l I

! l I

l Vent f1RMS-RE11A(B)] (LATER) Cpm (LATER) 1 (LATER) I l SGTS l I

l Effluent IIRMS-RE1031 (LATER)Com (LATER) (LATER) g l AREA RADIATION ,

g l LEVELS (Locations LATER) l (LATER)Mr g (LATER) l (LATER) l g i

I l I -

. I I . I i '

I I I I I I I I I I I I I l l l l l l l 1 1 I I I I I I I I I I '

l l -

l I -

1 I ' I i 1.

I l

, I I I

1 I l i I I I I I I I I I I

N/A I ll l l I

l _l N/A ll E0P-0003 l REV - 1 l PAGE 10 0F 15 l

l l ll l l l

l

. gl l

I i '

INSTRUCTIONS CONTINGENCY ACTIONS I l

l

~! l l .

I l 3.2 MONI'IDR AND CONTROL SECONDARY CONTAINMENT RADIATION LEVELS II l i l

l 3.2.'1 IF secondary,. containment HVAC l I

l exhaust radiation levels exceedl I I alarm level in Table II while l I

I performing Steps 3.2.4 or 3.2.5l I THEN isolate or confirm l I

I isolation of secondary l I

l containment HVAC. l 1

I l

! 3.2.2 E secondary containment HVAC C3.2.2 E space temperature is above I exhaust radiation levels exceed 212*F I (LATER) Cpm while performing l THEN stop SGTS.

I steps 3.2.4 or 3.2.5 l l I m l l I IF the space being exhausted l l l 5 below 212*F l l THEN initiate or confirm l g g

initiation of SGTS. l l 3.2.3 E secondary containment HVAC l C3.2.3 E bypassing high drywell ,

y

- isolates while performing l pressure and low RPV water leve% l g

Steps 3.2.f., 3.2.5 l secondary containment interlocks l AND l is required j E secondary containment HVAC l THEN bypass these per l exhaust radiation level is l contingency action details l l

g below (LATER) Cpm l (LATER). l THEN restart secondary l l g

containment HVAC. l l

.l I I l

-l 3.2.4 E any area radiation level l l g

exceeds its maximum normal l l operating level l l l

THEN isolate all systems that l l l

are discharging into the< area l l

'l except systems required to l l ;

l l

shutdown the reactor,, assure l l l

adequate core cooling or l l l

suppress a working fire. l l t . I I l

l 3.2.5 E a primary. system is l C3.2.5 E a primary system is l l

discharging $nto sn area l discharging into an area and an l l

THEN before any area radiation area radiation level exceeds l reaches its maximum safe its maximum safe operating l.

l l

operating level proceed to '

level in more than one area l+

EOP-0001; Instructions 3.0 and . THEN EMERGENCY RPV DEPRESSUR- l {~"

l

)

execute it' concurrently with IZATION IS REQUIRED. Proceed to. ['

l this procedure. E0P-0001; Instructions 3.0 [

AND execute concurrently with l l

this procedure. l3 l

l'j .l

'l I 1 I I -l ll l l l

l N/A ,l, N/A ll E0P-0003 l REV - 1 l PAGE 11 0F 15 l l

I i I ll l l l

,- e ,e,-, --v--- -,. - -

e m

?

l TABLE III l I

I !.

I Operating Values of Secondary Containment Water Levels 'l ,

I i I

l 1 SECONDARY l !l ;

I C0tfrAINMEP(T LOCA, TION ALARM MAXIMUM NORMAL MAXIMUM SAFE l l l l I l

l ll HPCS Pump Room 6" (LATER) (LATER) l l l

RuR xx l l l ,

and Pump Room B 6" (LATER) (LATER) l l 1 l l l RHR Pump Room C 6" (LATER) (LATER) l l 1 l I

)!

l l RCIC Pump Room 6" (LATER) (LATER) l l l l l RnR ax ! l I l and Pump Room A 6" (LA'ITR) (LATER) l l l l l l I l LPCS Pump Room 6" (LATER) (LATER) l l

1

! l Aux Bldg l

- ! l Floor Drn Sump (SA) 32 1/8" (LATER) (LATER) l l

l l Aux Bldg l l Floor Drn Sump (SB) l 32 1/8" l (LATER) (LATER) l 1 l l

. I I .I I 1 I .I I i 1 l I l l i I I I I I I I I I I I I I I I I I I I - 1 I .

I I I I I I e l I I l 1 I I I I I I I I I I I I I I I I I I N/A ' N/A E0P-0003 l REV - 1 PAGE 12 0F 15 I I ll l l l

l l I 1 INS'IltUCTIONS CONTINGENCY ACTIONS l l 1 'l l 3.3 NONITOR AND CONTROL SECONDARY CONTAINMENT WATER LEVELS I l tl l 3.3.'1 g secondaryfcontainment HVAC l l I

I exhaust radiation levels exceed l I (LATER) Cpm while performing l l

l steps 3.2.4 or 3.2.5 I l

I THEN isolate or confirm l I isolation of secondary !

l containment HVAC.

I !

3.3.2 E secondary containment HVAC l C3.3.2 E space temperature is above I !

exhaust radiation levels exceed l 212*F I

(LATER) Cpm while performing l THEN stop SGTS.

g steps 3.2.4 or 3.2.5 l AND l E the space being exhausted is below 212*F g l

g THEN initiate or confirm g initiation of SGTS. g l

I I I l

3.3.3 E secondary containment HVAC l C3.3.3 E bypassing high drywell ,

l isolates whila performing ] pressure and low RPV water level, ll l

steps 3.2.4 or 3.2.5 l secondary containment interlocks l AND l is required l l E secondary containment HVAC l THEN bypass these per l l

l exhaust radiation level is l contingency actions details l below (LATER) Cpm l (LATER).

l l l

THEN restart secondary l l l

containment HVAC. l l l I I

-l _ 3.3.4 E any floor drain sump or l C3.3.4 E any floor drain sump or l l area water' level is above its l area water level cannot be l l

maximum normal operating water I restored and maintained below l l level (Table III) l its maximum normal operating l l

THEN operate available sump l water level (Table III) l l

pumps to restore and maintain l THEN isolate all systems that l l

it below its maximum normal are discharging into the sump l l

operating leye1. or area except systems l l .

l required to shutdown the l l l reactor, assure adequate core l l . l cooling or suppress a working l l ; l fire. l l l l l l l 1 l l l l l l l l l l l l l l l l l ll l 1 l l N/A l N/A ll E0P-0003 l REV - 1 l PAGE 13 0F 15 l l l ll l l l

=1

-l; iirrs Pact inrENTIONALLY LEFT BLANK I )

.I l i 1 1 I I l r l '

I I I I I I

-1 I I I I- 1 I I I I

'l I I I I I I I I I l- 1 I I I I I I I I a

I '

-1 i

I

~l 1 I l I I I 1 I '

I I I I I 1 I I I I I I I I I I- < -

1 I I l -1 I I

.I I I I I . l .

-1 i l l I

..I' ..

l l l l : 1 I I I I I I I I I .I I I I I ll 1

.I' N/A -I N/A I E0P-0003 REV - 1 PAGE 14 0F 15 L

I I INSTRUCTIONS COPfTINGENCY ACTIONS I T I

I :I 1 I l 3.3.5 IF a primary syst'em is C3.3.5 E a primary system is .l l discharging Jato an area discharging into an area l l THEN BEFORE any floor drain AND a floor drain sump or area l I sump or area water level water level exceeds its maximum l I reaches its maximum safe safe operating water level in I I' operating level, proceed to more than one area l I

I E0P-0001, Instructions 3.0 and 1 THEN EMERGENCY RPV DEPRESSUR-I

! execute concurrently with this l IZATION IS REQUIRED. Proceed procedure. l to E0P-0001, Instructions 3.0 I I AND execute concurrently with !

. I l this procedure.

"END OF E0P-0003" l I I I I I I I I I I I I , I I

. I I .

I I I I I I , I I I I

1 I I I I I I I I I I I I I , I I I l . I I I I I I 1 I '

I l I I I I I I I l .

I I I 4

I . I I I I I I I I I I I I I ll 1 I i l N/A l N/A ll E0P-0003 l REV - 1 l PAGE 15 0F 15 l l l ll l l l 1

~~

- . g 1 I I

EMERGENCY PROCEDURE - LEVEL RESTORATION l t

l TABLE OF CONTENTS SECTION PAGE NO. ,

1.0 PURPOSE 3

- 2.0 ENTRY CONDITIONS 3 1

'3.0 OPERATOR ACTIONS 3

. TABLE A 4 l TABLE B 6 I l D

~

.I a

g.

I I

I

(

e

.. l t.

l W

I I l

.N/A l N/A l E0P-0004 REV - 1 l PAGE 1 0F 9 I ll l L

(NOTE 1]

I Boron' injection is required if the reactor cannot l l be shutdown (all rods inserted beyond ((06))) before l

suppression pool temperature reaches 110'F. ,g i I

[ NOTE 2]

RPV flooding is required under any of the following conditions:

I I

- Temperature near the cold reference leg instrument vertical l l

runs exceeds the RPV saturation limit. l l

l l

- RPV water level cannot be determined. l l

l 1

- Containment to annulus differential pressure cannot be l l

maintained below 15 Psid or drywell to containment differ- l l

l ential pressure below 25 Psid. l l l l

- Drywell temperature cannot be maintained below 330*F. l l 1 1 I I [ NOTE 3] l l

. l l

The most rapid way to initiate ECCS Injection Systems (HPCS, , I LPCS or LPCI) is to actuate the division initiate pushbuttons l l

l (on P601). , I l l

- l 1

l l l l l l l l l 1 I I I I I I I

I I I I l I I I . I I I l . l l e I 1 1 I I I I I . l I 1 I I I I I I l' 1 I I I I ll l 1 I l N/A l N/A ll E0P-0004 l REV - 1 l PAGE 2 0F 9 l 1 l ll l 1 I e

u .

- ami l 1.0 PURPOSE To restore RPV water level to above TAF.

~ ' I 2.0 ENTRY CONDITIONS 2.1 Enter this procedure from E0P-0001; Step C3.2.3, E water level cannot be maintained above -160 in, as read on wide range water j g

g level instruments. l 3.0 OPERATOR ACTIONS l i l

_ 3.1 Start the Combustible Gas Control Recombiners and Igniters. l l 1 l

3.2 Complete instructions and contingenecy actions (as necessary) l

.l 3.2.1 - 3.2.10. l I I I I I INSTRUCTIONS l CONTINGENCY ACTIONS l l

'l l I l

3.2.1 E while executing Steps 3.2.4 l l l

through 3.2.10, boron injection] l l- is required [ NOTE 1) l l l THEN proceed to AOP-0021 l e l

.l " Level /Powsr Control". l el l 3.2.2 H while executing Steps 3.2.4 l l l through 3.,2.10. RPV water levell l l cannot be determined l l l THEN proceed to E0P-0005 "RPV ~l l Flooding" [ NOTE 2]. l l 3.2.3 E while eiecuting Steps 3.2.4 l l l through 3.2.10, RPV flooding is ,

l l required .

l l THEN proceed to E0P-0005 "RPV l l

-1 Flooding" [ NOTE 2]. l l l 3.2.4 Line up for injection and startl C3.2.4 E less than 2 of the injection .l-l pumps in at least two of the subsystems can be. lined up, line l l following injection subsystems up_as many of the following l l [ NOTE 3]: alternate injection subsystems l l _ Condensite/Feedwater l as possible: l i (1103 .O.Psis) l Standby Service Water Inter- 1-l- HPCS (1103 - O Psig) l tie Valve [1RHS-MOVF094 and I l' _ LPCI A (310 - 0 Psig) l F096) on P061 l l- _ LPCI B (310 - 0 Psig) ((125 - 0 Psig)) l l _LPCI C (310 '- 0 Psig) Fire Protection System l l LPCS (500 - 0 Psig) '

(150 - O Psig) (See AOP-0050 l I " Station Blackout" for l l

details) l l SLC (test tank, with refill- l l- from CNS) (1103 - 0 Psig) l l SLC (boron inject) I I ECCS Line Fill Pumps l l- (10 Psig) I l' -l l 1-I l

'l -l: 1I I I I l N/A l N/A Il E0P-0004 l REV - 1 I PAGE 3 0F 9 l l l ll l l l

cx TABLE A l l l 1

-l l

tI L RPV LEVEL _l l INCREASING DROPPING lR l i I; l l

- -l g lP l RANGE .

[ l l

lV l l

.y l HIGH,-Greater Than or l l

.g lPl Equal to 485 Psig l STEP 3.2.6 1 STEP 3.2.9 ll l l

lR l l l l l

lE l- INTERNEDIATE l l l j lS .

(485 to 50 Psia) l STEP 3.2.7 l l l

lSl l l 4

l lUl LOW l l l l

lRl .(Less than 50 Psig) ,

l l lEl STEP 3.2.8 S1TP 3.2.10 l l l 1 1 I l (NOTE 4] l l .l l

485 Psig = RPV pressure at which LPCS shutoff head is reached. ,l l 50 Psig = RCI.C low steam pressure isolation setpoint.

~

l

, -l l

-l I l

.[ NOTE 5] l l 1 l CRD should be operated at maximum flow; operate l l 2 pumps; open flow control valve to keep pump l l- flow as close to maximum as possible. I I I I I I I I I l

I l- ~l l

-l l 1 1 '

I l l l . I

-l ,. 1 I I l- l l l

-I . l l .I I I I I

.l : l' I l 1 I

-l l

'l 1 - l 1. I I .I l N/A I N/A ll E0P-0004 l REV - 1 I PAGE 4 0F 9 I l- 1 II I I I

l

'l l l INSTRUCTIONS __

CONTINGENCY ACTIONS I 3.2.5 Monitor RPV pressure and water I I level and continue in this pro- II cedure at the step indicated in l

TABLE A [NUTE 4]. .I

1. E water level trend reverses or RPV pressure j g changes region l l l

THEN return to TABLE A and l g l

execute the applicable step.

l l l l

2. E RPV water level drops l l

below -144 in, while l l l l

performing Step 3.2.6 - l l

l 3.2.10 l l

J THEN prevent automatic l l

l initiation of ADS. l l l L I

l 3.2.6 E WATER LEVEL IS INCREASING l l M RPV PRESSURE IS HIGH l l THEN proceed to E0P-0001, Step , l l- 3.2.

, l 4

-l- .

l l 3.2.7 IF RPV WATER LEVEL IS C3.2.7 IF HPCS and RCIC are not l l INCREASING *. available l l AND RPV PRESSURE IS , AND RPV pressure is increasing, l l INTERMEDIATE THEN EMERGENCY RPV DEPRESSUR- l l THEN START-HPCS AND RCIC. IZATION IS REQUIRED. Proceed to l l ll E0P-0001, Step 3.0, implement l l 1. WHEN RPV water level ll concurrently with this procedure l l reaches +10-in. l l l O_R RPV pressure is dropping l l THEN proceed to E0P-0001, l l Instructions 3.2. ll' l l <

l l 3.2.8 IF RPV WATER LEVEL IS C3.2.8 IF RPV pressure is increasing l' l INCREASING' .

THEN EMERGENCY RPV DEPRESSUR-. l l AND RPV PRESSURE IS LOW AND IZATION IS REQUIRED. Proceed to l l NOT INCREASING E0P-0001, Step 3.0, implement l-l THEN proceed to E0P-0001, concurrently with this procedura l-l Step 3.2. .- l l ,. -l l 3.2.9 IF RPV WATER. LEVEL IS DROPPING C3.2.9 IF HPCS and RCIC cannot be l

.j, , M RPV PRESSURE IS HIGH OR Earted l' l: INTERMEDIATE- AND at least two injection l l THEN startiand/or verify subsystems are lined up for l l operating HPCS, RCIC and CRD injection with pumps running -l

~l [ NOTE 5]. , 'THEN EMERGENCY RPV DEPRESSUR- l l IZATION IS REQUIRED. Proceed to l l= E0P-0001, Step 3.0, implement l l concurrently with this procedure . l l l l- l l l ll l l l l N/A -l' N/A 'll E0P-0004 l .REV - 1 l PAGE 5'0F 9 l l l ll l l l-

I TABLE B l I l 1 l .I '

I 1 l l l I

l INJECTION SUBSYSTEMS ALTERNATE INJECTION SUBSYSTEMS l .!

'l '

I l l I SYSTEM PRESSURE RANGE SYSTEM l PRESSURE RANGE l l I '

l . I I l l Condensate /F-W l 1103 - 0 l Standby Service i ((125 - 0]) l g I Water l l l l l l

l HPCS l 1103 - 0 l l l l g l l l Fire Protection il 150 - 0 l l l LPCS l 500 - 0 l il l g g

g l l l ECCS Flush l 100 - 0 l l g l RCIC l 1103 - 50 l (from Cond Xfr) l l l l l l l l i

l LPCI l 310 - 0 l SLC l 1130 - 0 l l l l l l l l

l CRD l 1103 - 0 l ECCS Line Fill l 10 - 0 l

l Pumps l l l

l l Condensate 450 - 0 l l l

l (Condensate l l l j' l Pumps Only) l l l l l l l l 1 - 'I i '

'I I l l l I '

I I l l , I l l l l l 1 I I I I I l i I

-I I I .

I I I I I l . l' I I

.l .- ,

1

-l '

l I I I I

.I I l- I I I I I I I

.I I I I I I I I ll l l I

-l -N/A l- N/A ll E0P-0004- l REV - 1 l PAGE 6 0F 9 l ll-l i 1 I I

l- I l l INSTRUCTIONS l CONTINGENCY ACTIONS !

-l l '

l 3.2.9 (Continued) l C3.2.9 (Continued) I

.] l IF no CRD pump is operating, I l l AND no injection subsystem i l l lined up for injection.

y l l (No lined up subsystem has at g l l least one pump running.)

-l- l THEN start all pumps in alter ;

-\ l nate injection subsystems which l l are lined up for injection. g l- l l 1. E RPV water level drops to l l -160 in. l

.l AND no injection subsystem l l l' (capable of injecting into l l l the RPV at the existing i l

g I pressure per TABLE B) is l g

I lined up. '(No lined up sub-l l l system has at least one pump l I running.) l l

l THEN: l l

l l l

I l

a. WHEN RPV water level l e I l diops to -112 in, on l e I- EUEL ZONE Instruments; l i

l open one SRV. l l

I I I

b. WHEN RPV pressure drops l l

to'700 Psig; EMERGENCY -l l

g RPV DEPRESSURIZATION IS l l REQUIRED. Proceed to l l

E0P-0001, Step 3.0. l l.

l

! l

c. WHEN any system, I

! l injection subsystem or l l

. alternate injection sub-'l l

system is lined'up with l l l g at least one pump running l l l

THEN return to Step 3.2.5l .l

.l .

l l . I I I

.l l t

-l- '

l 3, s

'J l l '. ,

l 1 ~

l

.I l I l i I I I i

-l, / I

l 'I l l l l I I

-l N/h N/Ajj ll E0P-0004l- REV - 1 l PAGE 7 OF 9 .I I -

l ll l l 1

9 i

CAUTION #1 l l .<

,- i I Cooldown rates in excess of 100*F/hr *I i l l may.be required to accomplish this step. I i I

l l .,

I I

'l i I I I I I I

I l

l I

I I

I I .I I

I I

I I I I I I - I I I

~

I '

l 1

I I ,

I l l I I l- I l- 1 I I I I I ,

I l- 1 I I

1. I I .

I I I i . 1 1

l l' *

- I

! l- .

I

~

I '

l 1 I l -c l

i-- .l l l' . I I I l- I i i I

.I I

'l s I I I

! I I l

1 1 Il l I I l N/A .l -N/A ll E0P-0004 l REV - 1 l PAGE 8 0F 9 l 1 I ll l l l

1 I l

l INS'I1tUCTIONS CONTINGENCY ACTIONS l

'I t l

l 3.2.10 IJ_ RPV WATER LEVEL IS DROPPING C3.2.10 E RPV pressure is increasing I l AND RPV PRESSURE IS LOW THEN EMERGENCY RPV DEPRESSUR- ,I IZATION IS REQUIRED. Proceed '

I l (TABLE A) AND NOT INCREASING l- THEN start all pumps in ll to E0P-0001, Step 3.0, I l alternate injection subsystems l AND execute concurrently with I l which are lined up for l this procedure. l injeetion. !

l l l = :. .. . = u = :. :. :. :. : . .. . u s**** = = = u :. = = = = = = = u :. :. :. :. :. = :. = :. :. ****** l SEE CAUTION #1 I l

g l

l I l

-l 1. WHEN RPV water level drops l !

l to -160 in. !

l I MN I l

l I l

I a. Open all ADS valves. l a. E any ADS valves cannot l l be opened I b. Inject into the RPV withj THEN open other SRV's !

I the HPCS and LPCS l until a total of seven I (taking suction from thel valves are open.

I suppression pool). l g i ,

i l

c. E at least one Core l c. E no HPCS or LPCS system, l l Spray System is inject- l is injecting into the RPV g I THEN return to Step ing,into the RPV with l g I suction from the 3.2.9.1.

1 I suppression pool l l AND RPV pressure is less!

I l than'315 Psig l l

I THEN terminate injection l I l into the RPV from l I l sources external to the l prim'ary containment. l

d. E RPV water level is restored to -160 in. l l g

THEN. proceed to l l E0P-0001, Step 3.2. l l l

l

. "END OF E0P-0004" l l 1 1 1 i

I l i l I . I I I l I I I I l I I I I I I I I I

N/A I ll E0P-0004 l

REV - 1 l

PAGE 9 0F 9 l

l l- N/A ll l l l l l ll l l l

I EMERGENCY PROCEDURE - RPV FLOODING i

TABLE OF CONTENTS SECTION PAGE NO. l l

TABLE A 2 l l

FIGURE A 2 l l

1.0 PURPOSE 3 l l

2.0 ENTRY CONDITIONS 3 l l

3.0 OPERATOR ACTIONS 3 l 1

FIGURE B 8 ENCLOSURES Enclosure 1 - Full Size Figure A (RPV Saturation Temperature .

Curve) 12 e.

Enclosure 2 - Full Size Figure B (Maximum Core Uncovery Time-Limit)_ 13 l

>l. l

.I I I , I I

.$[

I y, . . I i

d, l .

'e i 1 N/A N/A ' E0P-0005 REV - 1 PAGE 1 0F 13 1

~

s

,g A 4

l - ~ s :"M A' TER.NATE RPV F'.00 DING ?RESSURE (MARF? ;

I

I l I i . NUMBER OF ! I l ! SRV 's OPEN' 4ARFP !

l i 7 155 Pstg* l l 6 185 Pstg* l l 5 225 Psig* I l

l 280 Psig* I l 3 380 Psige !

l 2 575 Psig* 4 I l '

1 or 0 1103 Psig* I I I *Above Centainment Pressure l l l l t I FIGURE A l l 1 I

RPV Saturation Temperature Curve l l l l 1 I I I

ru ng. c . wssa . u c m. l l

l T1% g h.-

.: .. ' . t .,, .y: g, wf...f,.. : AgW. at/ ,n ~

a gq r. - 2L4M,-,5. -.L:.,u%,r e,pp,, _ . % :.W: S. ;;;jf h :

4g . gy% % .- ag .g 1

c. ,-8 I

"L 4..:; g/ $y 4 l

.SY '.c,. , n '; c. .i.;*' ' -.; ,,* 'l ,, o

' . '. F y " ll*{;p - " s g

l h [,,,n,,',%-

l' ", . ]%Thi AW: : -

k. . % ~ .l % :Onj '

~ ?.c@,Wf? e-; . 4ffT. ;Tiif 7 -!:,[$jin t ~:

l $ . L

. Ityi, . .,$fg;! 3 w tgm t:[t. , . .e .i..1 - q y. ,;.

&; ?-

c. 'N h. '

, ' . ;(.'

.. : 7. WT irdV q 1. /,it . f*Lamiit - we.r 1 .~ ~

l

. tiltx%. -Q: gm p 9.; ; . '; < Mt. ,.;p4. ts'f;.

.. i.;.t l t # g $htig .3 g.,

g i s %jp' ;' ,; ln,s 4 l j pm g;3 : ; !* .: ' . d ;1 l

-4 ":7:*g.T ?% C r. . s *: T :ht.q:q pir en l

n .:

4y, . . r .7 s.(; u. v.

, y ,t 3 .(_ s g$ g bmoyg gnp .y.y.a,y,,,gg_ -

.

y. r,m .q rg.y h :) _ . , , __= _ ..1 ; y ;,.

qs + ; ,.3.-

< .,

y .?. . . t :y ;)_ .., g,.

g:q'

.y . l l -la e : ;.; . Y'.l .e ;; . ;$ i . :Y -. ,Y$ , _.?>-. k,kYj Y' 4 ?.,.(- .. ;. l l , .7 - ;~, .. y ., ; _,:, . . . .; ;. . - y $4;.Wky 9.- sy M,hi.f . ;l.,y ;. g see see ses see ses ese see see see is g a g are e o.w I I l ' l I I I i 11 1 I I l N/A l N/A ll E0P-0005 l REV - 1 l PAGE 2 0F 13 l l l ll l l 1 l 1.O PURPOSE l l l l To flood the RPV using all available injection subsystems. I I I l 2.0. ENTRY CONDITIONS ;l I . I l Enter from E0P-0001 or E0P-0002 when any of the folleving occur: I , I I - l 2.1 Temperature near the cold reference leg instrument vertical I I runs exceeds the RPV saturation limit (Figure A). I I I I 2.2 RPV water level cannot be determined. l I I l 2.3 Containment to annulus differential pressure cannot be l l maintained below 15 Psid or drywell to containment differential I l pressure below 25 Psid. I I I I 2.4 Drywell temperature cannot be maintained below 330*F. I I I l 3.0 OPERATOR ACTIONS I I I l Flood the RPV per the applicable sections: I I I l ! FLOODING WITH BORON INJECTION (3.1) I e I I FLOODING"WITH RPV LEVEL UNKNOWN - ALL RODS INSERTED ' I I I BEYOND [-[06)) (3.2). l l l FLOOD'ING WITH RPV LEVEL INDICATION - ALL RODS INSERTED BEYOND [f06)) (3.3). l 1 l INSTRUCTIONS l CONTINGENCY ACTIONS I ! 3.1 FLOODING WITH BORON INJECTION ! 1 l I ___3.1.1 Terminate and prevent all l C3.1.1 IF RPV pressure does not I injection systems except boron l decrease below MARFP (TABLE A) g I and CRD from injecting unt'il l with 3 minutes g I RPV pressure is below MINUMUM l THEN continue in this procedure ALTERNATE RPV FLOODING PRESSURE l at Step 3.1.2. g (MARFP); TABLE A. l g 3.1.2 Open at least 2 SRV's; place C3.1.2 IF less than 2 SRV's can be open the control. switches to OPEN. l THEN continue with Step 3.1.3 g -~ l even if no SRV's can be open. I I I I I . I I I I I I I I I I- l I I I I N/A N/A E0P-0005 REV - 1 PAGE 3 0F 13 I I il i I I ( CAtTTION #1 l A rapid increase in injection into the RPV may I !- l induce a large power excusion and result in ;I l substantial core damage. I l 1 I I I TABLE A I .I I l I MINIMUM ALTERNATE RPV FLOODING PRESSURE (MARFP) I I I I -l NUMBER OF 1; I l I SRV's OPEN MARFP I l ~ l l 7 155 Psig* , I- ! l 6 185 Psig* l I l 5 225 Psig* I I l 4 280 Psig* I ll 3 380 Psig* l l 2 l 575 Psig* 1. g I 1 or 0 l 1103 Psig* l l l

Above Containment Pressure g

-l . l .I . , I I . I I I l l l , I I I I I I I I: I I I I I I I I I I , I I I - I I -l : I .I . l l 1 I . l l - 1 I I I I I I I . I I I l- , I I l l I I I ll 1 I I N/A N/A E0P-0005' REV - 1 l PAGE 4 0F 13 I I ll l l 1 i I i l INSTRUCTIONS CONTINGENCY ACTIONS I < l l 1, I l l 9 l SEE CAUTION #1 .l l

- - - - m = = u u q = u u m u = u = ;.u u u u;.u u = = u = u;. = = = ='I l

I~ l l 3.1.3 IF RDV pressure is below MARFP l C3.1.3 E at least 2 SRV's are not open ! OR the RPV pressure does not ! l THEN commence injection and l l slowly increase flow into the l stabilize above MARFP ! I l RPV with the following systems AND all available preferred I l until at least 2 SRV's are open pumps are being used I @ RPV pressure has stabilizedl THEN commence and slowly I above MARFP per Table A; use l increase flow into the RPV with I the following preferred pumps: l the following until 2 SRV's are I _ Condensate /Feedwater Pumps l open: g I CRD (Maximum Flow) l HPCS I l LPCS I 1. Maintain at least 2 SRV's l LPCI l open and RPV pressure above l Standby Service Water Cross-I MARFP but as low as l tie (Open Valve [1RHS-MOVF094 g I practicable by throttling l and F096] on P601) l ! injection flow rate. l Fire Water System g I (see A0P-0050) I g

2. E only. low pressure systemsl ECCS Flush Connections from *l are available l Condensate Transfer >l THEN open additional SRV's l SLC (Test Tank) l as necessary to obtain MARFPl SLC (Boron Tank) l y

below the injection / l l g alternate injection system l l g discharge pressure. l l l I l g

3. WHEN all control rods are l l inserted beyond position l l l

g [06] l l THEN proceed to Section 3.2 l l l or 3.3 as applicable. l l l l , I I i l . I I I I I l l l 1 1 '. I I l l l 1 I I . I I I I I I I I I I I I I I I I i 11 1 I I l N/A l N/A ll E0P-0005 l REV - 1 l PAGE 5 0F 13 l l l ll l l l =l TABLE A

I l I I

MINIMUM ALTERNATE RPV FLOODING PRESSURE (MARFP) 'I .I I l I I l . NUMBER OF 1 I l I l ' SRV's OPEN MARFP l l l l l- 7 155 Psis* l I l 6 ' ~l 185 Psis* I l 5 ' 225 Psig* l i I ! 4 l 280 Psig*

l. l I 3 l 380 Psig*

l l I , 2 l 575 Psig* l l l 1 or 0 l 1103 Psia

l

Above Containment Pressure l g

i I I I I l- I I 1 I: I I I I I l I l . l I

I l

I l . l I I ' I -l

1. I I I I I

-l I 1 1 I I I I l- I l ' l I l-I- I l- I i I I I '. l . I -l ; I I I , . . I l I . 1 l I I I I I .I I I l i I .i i 11 I i N/A 1 1 l l N/A ll E0P-0005 REV - 1 I l l -l PAGE 6 0F 13 l l 11 I I l 2l O j l g l l INSTRUCTIONS CONTINGENCY ACTIONS l t ll I } l l 3.2 FLOODING WITH RPV LEVEL UNKNOWN - ALL RODS INSERTED BEYOND ((06)) l il l :I !! l 3.2.1 Open at least.3 SRV's; place l C3.2.1 E less than 3 SRV's can be open I ,' I the control switches to OPEN. l THEN continue in this procedure l l l even if no SRV's can be open. l l 3.2.2 WHEN at least 3 SRV's can be l l l l opened l l OR if a HPCS or feedwater pump l I I is' running or in STANDBY I I THEN close the following: I I I I MSIV's l I Main Steam Line Drains [1B21- l I I -F019, F085, F086, F067] l I I RCIC Steam Isolation Valves l I I -[1E51-MOVF063,F064] l I I RHR Steam Cond Isol Vlv l [1RHS-MOV52A, 52B] l 3.2.3 E RPV pressure is below MARFP l C3.2.3 E at least 3 SRV's are not open (TABLE A) l OR the RPV pressure does not l I THEN commence injection and ( stabilize above MARFP

g I slowly increase flow into the l AND all available preferred ' l

! RPV with the following systems pumps are being used l ! until at least 3 SRV's are open THEN commence and slowly g ! AND RPV pressure has stabilized l increase flow into the RPV with l above MARFP,per Table A, use l the following until 2 SRV's are l the following preferred pumps: l open: l l g _ Condensate /Feedwater Pumps l HPCS l CRD l LPCS g l l LPCI g l g _ 1. Maintain at least 3 SRV's l Standby Service Water Cross- l open and RPV pressure above I tie (Open V1vs [1RHS-MOVF094 l g MARFP but as low as and F096] on P601) l l Fire Water System practicable by throttling a l l g injection flow rate. , l ECCS Flush Connections l g from Condensate Transfer l g

2. E only'. low pressure systems SLC (Test Tank) l g

are available H SLC (Boron Tank) l THEN open" additional SRV's l l as neces'sary to obtain MARFP l l l below th'e , injection / l alternate injection system l l l l dischargefpressure. l l l l l l l . I I I I I , I I I I l 1 -l l l l l l ll E0P-0005 l REV - 1 l PAGE 7 0F 13 l l N/A l N/A ll l l l l l ll l l 1 O yg -- - - ~ - I . l The intent of "...RPV water level ca be - i l . determined..." is that there are no ' l elevated containment or drywell temper- i l atures.which could cause flashing of level l l instrument reference legs. 1 I I I I I FIGURE B l . 8 l l Maximum Core L'ncovery Titre f.imit I I i l i I I i . I II:.- . i l - - ,i.. :r i i lil, .::. ,,li g, i l l i ii: iii,-

?;j l

l .;l .l ~~~ ' ' Wl8888 M N file LBIIT . , l l - ..: i .j ; i ! I $ : ...: - . . : , p: ,; - l Ti ! l 1 :- l!!' m _c .: ; ! . l :. l;; I ] I . I . . i;.. .. .. ... i li!, ,!,. 1 :i ,1~

i. ::,l l ! i- ,;

.i,. I

i !i.

s ,. 4 - - I

ii: ! *

l i '

oli i. j; ,! I l 3, I:i ", - i . i _f : it.! .r l i ~ l ; , l ; s-l ! j d Aj e: i. .. , . ' ' J ',l I II I !!'!lli5 'll! .' ., l ' jdj - ili .I,!i .' ! , ! !i .I jl [ .. l ! I ,, ii!, lllill!!:h.! """I^*i ) l . l! . l l l ':i. 'L " l !I .I.ll 1 : .i .~ : i j l l l ,, l i i, ,b , ,,e , l t - 4 9 ]I . ji I 1 :

j. I a

l j i

j. ...

.,g, 3, i. ; , g i " l a ' h i i ti! !;: w' .-- ,, ! l 1 I , l I I r .

i. .i ,

! l l l ...= ! , l l ACCEPTA5Le 3000e ' l l ,.,,,, ..... ,'. .m----""""'"" "'I I i y , t, - l i i l . i h o I n are., "*., . u c.i.3 I I I I < l l l l l l ' l. .i . 1 I l: l 1 l 'l I I I . I i l l l l . l I ! I I ll l l l 1 N/A l N/A ll E0P-0005 [ REV - 1 l PAGE 8 0F 13 l l l l ll l l l \ I I T l INSTRUCTIONS C0ffrINGENCY ACTIONS I 'I I I 3.2.4 IF while executing Step 3.2.5 l l RPV water level can be I ; l I determined [h10TE 1] l 11 TEN proceed' to Section 3.3. I I L l l 3.2.5 IF it can be determined that l C3.2.5 IF water level indication is not I l 5e RPV is filled l Nstored with the maximum core ! I l OR that RPV pressure is at uncovery time limit (Figure B) I least 80 Psig above containment after terminating injection into the RPV ! pressure I l THEN terminate all injection 1 THEN return to Instructions ! I into the RPV for no longer thanl 3.2.3 I I the Maximum Core Uncovery Time l AND continue to repeat ! I Limit (Figure B) and reduce RPVl Instructions 3.2.3, 3.2.4 and I I water inventory to bring level l 3.2.5 until RPV water level I l within range of operable level l Indication is restored. indication. l l I I I I I I , I I , I I - 1 I . I I I - I l .I I I I I I I I I I I I I I I I I e i l i I I I I I ., I I I l . I I : I I I I I I I I : I l l I I l l I I l l l l l l l l ll E0P-0005 l-REV - 1 1 PAGE 9 0F 13 I l N/A l N/A ll l l l 1 I ll l l 1 r = Tals PAos ImwrI0nAur urr sIme: 1 I 1: - i I 1 i I

I

-l i l i i i l I I I I l I 1 1-I I i I I l I I I I I I I I I I I I I I i I . l

l. .

i l I . i I I l I I . I I I I -1 I I I I I I I I .I , I I I l I I I I - I i . I .I l . .l. '.- I .I l I 1 .l . I -- l 1 i - I 1 I I l -1. 1 I ' l l l-I -l N/A:l N/A l E0P-0005 REV - 1 PAGE 10 0F 13' I l- 11 1 I I L l l : i INSTRUCTIONS l COPTTINGENCY ACTIONS I l l l l 3.3 FI40 DING WITH RPV LEVEL INDICATION - ALL RODS INSERTED BEYOND ((06)) I : l 3.3.~1 Open at least,2.SRV's; place l II l C3.3.1 H less than 2 SRV's can be open I l the control switches to OPEN. i THEN continue in this procedure ! l l even if no SRV's are open. I l _ 3.3.2 WHEN at least 2 SRV's are l ! l opened l ! l OR if a HPCS or feedwater pump l l l 1s running or in STANDBY l I l THEN close the following: l I l MSIV's l ! l [MainSteamLineDrains[1B21- l l F019, F085, F086, F067] l l ~ RCIC Steam Isolation Valves l I l [1E51-MOVF063, F064] l ! l ~ RHR Steam Cond Isol Vivs l ! I [1RHS-MOVS2A,52B] l l l l 3.3.3 Commence injection and increase l l I flow into the RPV with the g l l following systems. Use only l g I those systems required to cause ' g I RPV water level to increase l ' g I (listed in' order of preferred I , g use): . I CE g ~ l I g _ Condensate /7eedwater Pumps l l l _ HPCS (Suction from CST) l g I _ LPCS l I _ Standby Service Water l l I _ Fire Water System l l l l _ ECCS Flush Connections from l I l Condensate Transfer l l _ ECCS Line Fill Pump l l l l _ SLC (Test Tank) , l l _ SLC (Boron Tank) l l . l I _ 3.3.4 WHEN drywell to containment ' l I differential pressure can be l I l maintained be. low 25 Psid l M containment to annulus l l I differential pressure can be 1 l I maintained below 15 Psid l THEN proceed'to E0P 0001 "RPV I l j- - Control", Instructions 3.2 and l [ l g 3.3.5 and execute these steps concurrently. l g l "END OF E0P-0005" l l l l l l l l N/A N/A E0P-0005 REV - 1 PAGE 11 0F 13 l l l ll l l l l E '. '. _ s . _ - ._ s :: ; i, .u i:-; Temperature ('F) Beer Cold Referesse Lag Isetnment vertisal Buns ~ w * * , we e m m 4sr ._ . , - ~ .~. - . -: 1 l a_ -. 33~ -]['I. ."w- ;; y;.- f. . EIEi - g' .+ - 1 A. .. w I +:; ..& = .y == j +.

Tid l.' -

yy-- -= ~ I I . _- as i I g i l i l 1 I i I l , u 8 s , ~- l m l l , , 7p.t ; l ~ E :. { ~' I ..w I 1,, _ l t, I I I I S .9 I i , I j i ] . l I l E l I l = i l 3 I I I l l i l l I - g l l 1 l I . I ~ I l ( ENCIASURE - 1 PM 10F1 l l E0P-0005 REV - 1 l l P M 12 0F 13 I l 1 ( g . , - - _ _ . - . . _ . . - - - _ . - - = - - . . . . - . _ . . . - . - . - r

p. . . . - .

E ?.C C 5i.'R E . : r-A 3-' E' ~~ L'^~ E C' ' '%-'" 3' -

n';'- ' - -.-

~ * '-

~- .. . . . _ . . . _ _ . __N- , s x i_._.... m__ _ i. i . ~ ...=.. g ._ E . .. n . I s,_.._~-.-- ' l . I * - I g .. . _ = , i I . _ _ . _ . _ . . _ + l i.. _$a , = .- ' .a.: E. ~ l , , , _ , , _ , . . . . _ . _ . . _ . - . . _ _ _ . 1 _ _. . .sm ,3 I . . _ . . . .. . . _ . . . . . _ .- c_ u wa I I -. l 4 . . _ .._ , , s l E -..j . =. . ..__ ..__... n.:_...:.:: :.-- - i .====:s_ , _-. : l, I . l . . . ......._..._4 . .- . , l , . . _ _ . m e. ~. . a . . . . _ . . . . . . . . . _ - l I 8 ... l I l , . . _ . . . ._.... _... ..- = e t . . } . . .. .- . _ . . , _ _ . . =. . . . . . . - . _- l

t. .-

l .. .. . . l t * ~~ ~ L. .. . . . . . . . . . .e I l . . . . . _ . g l ...... .. . . I _ _ ... _ - - . ,. l .- _. .. . _ .. - l ,, , , . , ..[ g .g: .c.<* . c , '.. . .. '.,'".Ju.r. . i . =.= .r=sym_ur"i. g messamm R 3 2 2 2 * ' i . ( metosuaB - 2 PAGE 1 0F 1 EOF-0005 aEV - 1 PAGE 13 0F 13 g . : 4 ? 9 . ..a..eg.. *- ,t . _ - , - - - - -

RBG-19-891, Forwards Emergency Procedure Guideline Deviation Justification Forms Per SER Section 13.5.2.3 Confirmatory Item 60.Evaluation Underway to Ensure That Emergency Operating Procedures Consistent W/Fsar Design Basis

Text

Dear Mr. Denton:

=.9._

Navigation menu

RBG-19-891, Forwards Emergency Procedure Guideline Deviation Justification Forms Per SER Section 13.5.2.3 Confirmatory Item 60.Evaluation Underway to Ensure That Emergency Operating Procedures Consistent W/Fsar Design Basis

Text

Dear Mr. Denton:

=.9._

Navigation menu

Search